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TRANSCRIPT
UCRL-CR-128874
S/C- B333556
ACAB Software Upgrade
J. SanzJ. M. Balmisa
Disckdmcr -‘his documentwaspreparedasanaccountof worksponsoredbyanagencyoftheUnitedStatesGovernment.NeithertheUnitedStatesGovernmentnortheUniversityofCalifornianoranyoftheiremployees,makesanywamnty,expressorimplie~orassumesanylegalliabilityorresponsibilityforrheaecuraey,completeness,orusefulnessofanyinformatio~apparatus,productorprocessdiselose&orrepmentsthatitsusewouldnotinfringeprivatelyownedrights.ReferencehereintoanyspeMIccommered“ produc~process,orservicebytradename,tmdemarkmanufactmer,orothenvise,doesnotnassarily constituteorimplyitsendorsementrecommendationorfavoringbytheUnitedStatesGovernmentortheUniversityofCdifomia.TheviewsandopinionsofauthorsexpressedhereindonotnecessarilystateorreflectthoseoftheUnitedStatesGovernmentortheUniversityofCalifoM andshallnotbeusedforadvertisingorproductendorsementpurposes.
ThisworkwasperformedundertheauspicesoftheU.S.DepartmentofEnergybyLawrenceLivexmoreNationalLaboratoryunderConrraetw-7405-Eng43.
.,.
Report on:
ACAB software upgrade
(contract B333556)
J. Sanz(l) and J.A4. Bahnisa@)
October 1997
‘%stituto de Fusi6nNuclear(UPM)*PerinanentAddress:ETS IngenierosIndustrialsUniversidadNationalde Edu&cion a Dktancia(UNED)
‘2k%Dat ETS IngenierosIndustrials (UNED) andInstitutode FusionNuclear(UPM)
*PermanentAddress:StafFConsejode SeguridadNuclear(CSN)
ACAB Software upgrade
J. Sanz and J.Al. Balmisa
Summary of the contents
This report, according to the subcontract B333556 mquimments, addresstwo issues, stated as:
i) “Selection of the most current nuclear data librariesavailable”.ii) “User’s manual of the updated ACAB code”.
After a general summary of the major features of ACAB (Section I),highlitingthe new capabilities included in the present version of ACAB, theqort is dividedin sections structured as follows:
i) Firstly, we address the issue of the nuclear data libraries selectedas staxting point in preparing the libraries to be used directly by ACAB.Section II describes the main features of the selected libraries.h Section IV,the impact of using these libraries in Inertial Fbsion Energy, II%,applications is assessed by comparing activation Rsuks obtained usingdifferentactivation cross-sections data libmries.
ii) Secondly, the points considered are the processing of [ibraries andlibraries adapted to be directly read by ACAB. The “processing” effortsmade whitin the fmme of this project have been fmussed on theCOLLAPSE code. Important modificationshave been made, and in SectionIV we provide an overall description of the new version. The content of thedata bases employed by the updated ACAB code are described in Sectionv.
iii) Thirdly, the input data file for running ACAB is dealt with mSection VI, and some example problems am discussed in Section VII.
iv) Fiilly, regarding analysis of aet.ivation resuI@ we described inSection VIII the updatedversion of the CHAINS code.
I
.-
. ....+_.=...-.-...%..... . . .. .. .
CONTENTS
I.-
II.-
III.-
IV.-
v.-
VI.-
Page
Major Features of ACAB ................................................................... 1
Selection of Nuclear Data Libraries ................................................. 6
A.- Activation Cross Section Data Library: FENDL/A-2.O .....6
B.- Decay Data Library: FENDL/A-2.0 ....................................ll
C.- Fission Yield Data Library: JEF-2.2 ..................................... 13
Comparison Between Results Based on DifferentCross Section Data Libraries FENDL/A-2.0, EAF-4.1 andEAF-3.1 ..............................................................................................2o
COLLAPSE Processing Code .........................................................26
Data Libraries for ACAB .................................................................36
Input D~ription ............................................................................42
A.- Block# l ..................................................................................43
B.- Block# 2 ..................................................................................46
C.- Block # 3 ..................................................................L...............49
D.- Block # 4 ..................................................................................5l
E.- Block # 5 ..................................................................................52
F.- Block # 6 .................................................................................53
G.- Block # 7/8 ............................................................................. 54
H.- Block #9 .................................................................................57
I.- Block #/10 .................................................................................58
J.- Block #11 ................................................................................59
VII.- Example problems ...........................................................................M
VIII.-Pathtvay analysis.CHAINS code ...................................................78
IX.- References .........................................................................................88
1
i
LIST OF TABLES
Page
Table I.New capabilities included in the updated ACAB code.
Table 2. Reaction types included in FENDL/A-2.
Table 3. Sources for the cross-section data of the inporhzntreactionszddibraryof FENDL/A-2.O
TabIa 4. Sources for the cross sections data of the inportmt reactionsublibnzryof FENDL/A-2.O.
Table5. Modes of decay and number of ground state and isomeric statedaughters produced in each mode.
Table 6. Fissionable nuclides with fission products yields datain JEF-22.
Table 7. Sources for neutron-induced fission products yields.
Table 8. Comparison of SLB-concentration limits (in wt fraction)obtained from EAF-3.l,EAF-4.1 and FENDL/A-2.O.
Table 9. Comparison of remote recycling concentration limits(in wt fraction) obtained from EAF-3.l,EAF-4.1 andFENDL/A-2.o.
Table 10. Comparison of hands-on recycling concentration limits(in wt fraction) obtained from EAF-3.I,EAF-4.1 andFENDL/A-2.o.
Table 11. Limits on element concentrations (in wt fraction),andcontribution of dominant radionuclides.
Table 12. Energy group boundaries for the Vitamin-J 175-groupstructure.
Table 13. Energy group boundaries for the GAM-11100-group structure.
Table 14. Energy group boundaries for the 175-group energy structure.
Table15. Type of tables that are output by ACAB.
Table 16. Example ACAB output. Isotopic masses
4
8
9
10
12
14
15
22
23
24
25
33
34
35
48
69
11
.. ...................... ..... ........ .
........ ... . ... .... . ... ... ...-.>---——-- .. .. ....................
Table 17. Example ACAB output. Radionuclide activities. 70
Table 18. Example ACAB output. Decay heat. 71
Table 19. Example ACAB output. Contact Tray. 72
Table 20. Example ACAB output.Contact Bremsstrahlung. 73
Table 21. Example ACAB output. Calculated y-ray spectrum. 74
LIST OF FIGURES
Figure 1. Relative locations of the products from all the nuclear reactions,with exception of fission, that are considered by ACAB. 5
i —.—....
-,-........
... ..... . . .. . ..-...-—- .. ....-- .- —.—.— ——--- .. ....... . .
I. Major features of ACAB
The ACAB (Activation ABacus) code is a computer program designed toperform activation and transmutation calculations for fwion applications. Themain computational algorithm is based on that of the ORIGEN* code, and theprogram structure is based on that of the ACFA’ code.
ACAB is able to perform space-dependent inventory calculationsallowing for a very flexible geometry and neutron flux description. The codesolves the general nuclear transmutation chains for multidimensional neutronflux distributions. One- and two-dimensional multigroup neutron fluxesgenerated by discrete ordinates transport codes can be used. In addition, ACABcan use three-dimensional neutron fluxes generated by Monte Carlo neutrontransport codes allowing inventory calculations to be performed for complexgeometries. The multigroup neutron fluxes maybe given in an arbitrary groupstructure.
ACAB considers decay transitions that proceed from the ground, first,and second isomeric states. All the neutron reactions that may occur in thedifferent components of a fusion facility are treated in the code. Therefore, thereactions occuring at energies ranging from the thermal region to 20 MeV areconsidered. Each of the neutron reactions may proceed from a target atom inthe ground, first or second isomeric state and result in a product that is in theground, first or second isomeric state. ACAB is also able to deal with sequentialcharged particle reactions as an additional mechanisms for the production ofactivitv..
The code has been recently modify to fully treat actinides and fissionproducts. In the inventory calculations you may consider up to 61 fissionablenuclides with the associated fission yields. Explicit information for independentyields coming from 19 fissionable nuclides is currently available. Fission yieldsfor around 14S0 nuclides can be managed. In figure 1 we show the relativelocations of the products from all nuclear reactions, with exception of fission,that are considered by ACAB.
ACAB has the ability to simulate realistic operational scenarios of verydifferent nuclear systems. In particular provide an accurate and efficientmodeling of the pulsed schedule for inertial fusion experimental facilities, suchas the National Ignition Facility, NIF. Any arbitrary irradiation/cooling historyis represented by a series of irracliation/cooling periods, defined as a unit,which can be repeated a specified number of times and followed by distinctirradiation and cooling periods.
In addition, some modifications have been recently included allowing for“restart” options, which can be very useful to make easier activation modellingof hohlraum targets, and fusion reactor materials under the pulsed irradiationscenarios corresponding to Inertial Fusion Energy ( WE )power plants.
ACAB’s primary result is isotopic concentrations as a function of time foreach spatial interval and/or zone defined in the system. From the isotopicconcentrations, ACAB is able to generate radionuclide activities, afterheat,decay gamma spectra, contact dose rates, waste disposal ratings, and biologicalhazard potentials. Other quantities that depend upon isotopic concentrationsand/or radionuclide activity can easily be added to ACAB.
In addition to the calculational faalities, ACAB also performs analysis ofthe activation results. Critical radionuclides are identified and pathwayscontributing to their production are evaluated.
Work in progress is mainly focussed on the following issues:
Computatwnal procedure for activation analysis of targets in inertialexperimental facilities similar to the National Ignition Facility (NIF). Acomputational procedure is being developed to compute the neutron-inducedradioactivity associated to the targets used in the operational escenario of NIF.This enable ACAB to deal with the activation of the materials coming from D-Tand non-tritium experiments, which are succesivelly deposited on the chamberwall and exposed to the neutrons of subsequent shots.
Computationalmethodsfor uncertainty analysis on activationcalculations.Acomputational method is being implemented in ACAB to perform uncertaintyanalysis on activation calculations due to uncertainties in activation crosssections. This method is based on a first order Taylor series approach, and inthe use of original algorithms to compute de derivative of the matrixexponential funcion. The method can be employed to compute the uncertaintyin activation results coming from the uncertainty in each cross section, and topriorize the cross sections requiring more accuracy.
Some preliminary work has been also done to perform uncertaintyamlysis by the Monte Carlo method. This method will provide uncertainties inthe activation results due to the uncertainties of the total set of cross sections.
Sim@ifzedmethoa%jbrd.eulingwithactivationunder pulsed irradiationregimesof IFE power reactors. When dealing with the problem, the methods currentlyimplemented in ACAB, although with high accuracy, maybe questioned underthe tradeoff between accuracy and time consuming. Therefore, someapproximate methods will be implemented. The activation of several materialswill be studied by the simplified methods and the realistic one, in order todetermine which approximations, if any, could be acceptable to replace thecurrent solution in modelling of pulsed irradiation under IFE power plantconditions.
Adjointactivationcalculations.Work is currently underway to make ACABable to performe ad]oint calculations. This would provide straightforwardwhich initial isotopes generate any radionuclide of interest and in what
. .
2
proportions they contribute to that production.
The performance capability of ACAB has been tested in severalbenchmark exercises. It is worth mentioning the International Atomic EnergyAgency (IAEA) Second International Activation Calculation BenchmarkComparition Studys. The IAEA Benchmark was based on four criteria: (a) abilityto read standard libraries (cross sections GAM-11 or Vitamin-J groupstructures); (b) accurate (to within about 570) calculation of quantities ofisotopes in multistep pathways; (c) ability to calculate light nuclide (H and Heisotopes) production; and (d) ability to treat isomeric states present in thelibraries. Out of eleven worlwide codes participants of the study, ACAB wusoneof the only twocodes that was able to satisfy all four criteria, and was assessed as“suitable and satisfactory” for ftkon applications.
The potential of ACAB for the I.FE applications has been demostrated ina significant number of studies .It can mentioned ( in addition to the thosedirectly related to members of the Instituto de Fusion Nuclear), the applicationsperformed by the Department of Nuclear Engineering at the University ofCalifornia,Berkeley; the activation assessments of the conceptual reactor KOYO,proposed by the Institute of Laser Engineering (ILE) at the University of Osaka;and particularly, applications for IFE and NW, and support for maintenanceand the development of ACAB by Lawrence Livermore National Laboratory.
Table 1 gives a description of the major new capabilities included in thepresent version of ACAB, which enhance significantly the former version ofACAB -2.0’. The code currently runs on Crays and on an HP/735 workstation.ACAB is written in standard FORTRAN 77, so porting it onto other Unix-basedwork-stations should not be difficult.
3
. ...—--- ------- .
I
Table I.- New capabilities included in the updated ACAB code.
1.- Operational scenario (irradiatiordcooling history).
- A restart option is included to make easier dealirradiation.
- More options have been included to make easierarbitrary irradiation scenarios.
2.- Nuclear processes.
with pulsed/ intermittent
modelling and input for
- Neutron reactions added: (n, 4n), (n, 4n-m), (n, l-in-s)and (n,F).
- Generation of fission products.
- Modifications for dealing with ~ and electron capture transitions resultingan excitated state product. Some trucation errors have been removed.
3.- Nuclear data libraries.
- Decay data library from FENDL/D-2.O.- Photon yield library from FENDL/D-2.O.- Activation cross section library from FENDL/A-2.O.- Fission yield data from JEF-2.2.
in
- These libraries have allowed to inaease significantly the number of nuclidestreated by ACAB.
4.- Decay photons.
- Photons produced from second isomers have been added.
5.- Processing/collapsing of libraries.
- The COLLAPSE code can condese cross sections to a 175-group TARTstructure.
- COLLAPSE produce weithed fission yield cross section libraries.
6.- Pathway analysis.
- The CHAINS code has been modified to include all the nuclear processesimplemented in the present version of ACAB.
-Some inconsistence between identification numbers of neutron reactions anddecay processes have been removed.
Figure 1. Relative locations of products from all the nuclear
reactions, with exception of fission,that are considered byACAB.
Z+2
Z+l
z
z-1
z-2
{dn) (nSn)
(rlmt)
I(m)
I
(m-)
(pm)
(a)
(*)
(*P)(n,t)
(n~d)
(nra)(n#He)
(3H@
(d~)
(GM
originalNucleus
(WO
(rd
(-p)
(n,3He)
(-)
(t#n)
(mY)
(Wp)
(tip)
Z-3 -
Z4 m(nm2a) (n2a)
N4 N-3 N-2 ~-l N N+l
Neutron Number
Note: ACAB considers twenty one netron reaction types (fission plusanother 20 reaction types) and seven sequential charged pax-ticksreactions types. The target can be an atom in the ground,fkst orsecond isomeric state. Neutron reactions may result in a product thatis in the ground, first or second isomeric state
5
1 ———..... . . ...-=. ............ .... -.
...... .......... .. ...... . .. .
II. Selection of nuclear data libraries.
The libraries selected as starting point to prepare those directly used byACAB are the following
- FENDL/A-205 is selected as the activation cross-section library.
- FENDL/D-2.OfI is selected as the decay data library (it includes also thephoton yield data ).
- JEF-227 is seld.ed as the fission yield data libary.
In the rest of this section, the main characteristics of these libraries aredescribed.
A.- Activationcross section data library FEND~A-20.
The FENDL/A-2.O libra~ is a neutron cross section data base producedwithin the IAEA FENDL project which has the goal of providing acomprehensive Fusion Evaluated Nuclear Data Library for predicting allnuclear processes in fusion devices.
The FENDL/A-20 file containk data for all stable and unstable targetnuclides with half-lives longer than ?4 day. If a reaction produces isomers thecross section for the ground-and isomer- stale are given separately. TheFENDL/A-2.O includes 739 target nuclides from H (A=l, 2=1) to Cm (A=248,2=96) with 13,006 reactions, in the incident energy range up to 20 MeV. Thesereactions are significant in producing activation both at short and long coolingtimes. The reaction types and number of reactions for each type included in thelibrary are given in Table 2, and the sources for the cross section data of thesereactions are listed in Table 3.
The FENDL/A-20 activation library can be considered as formed bytwo parts i) a sublibraryof important reactims for fusion application and ii) abasiclibrarywhich complements the “important reactionsublibra@.
The FENDL/A-2.O Sublibrary of Important Reactions contains 398reactions important for fusion reactor technology in general, although it was atfirst particularly aimed for activation studies within the ITEl? design. Thesources for the cross section data of these reactions are given in Table 4.
In the FENDL/A-2.O Basic Library all the cross-section data importanthave been selected from the European Activation File version 4 (EAF4.l)S.
Considering the two parts together, we have that in FENDL/A-2.O thebulk of the data is EAF-4.1, with around 240 selections (see Table 4) from ADL3, JENDL/A-3.2, FENDL/A-l.l. ENDF/B-VL IRDF-90.2, IRK and CRP.
6
.... ....... .. -------------------------- ------.–-—-— .—
It has been emphasizeds?g that the basic library contains evaluatedneutron activation cross sections selected from existing activation data files. Inassembling this libraxy, no additional evaluation work was performed in orderto improve evaluations; ordy existing evaluations were considered forinclusion. Therefore, in many cases the dala given are theoretical estimateswithout or with limited experimental verification so that the data uncertaintymay be significantly higher than for those evolved from careful evaluation andvalidation (such as the important reactions).
.. :
., .
I
Tabla 2.- Reaction types included in FENDL/A-2.O. [Ref. 5]
N,2NN,3NN,4NN,GN,FN,N
N,NDN,NPN,NAN,NTN,NHN,2PN,TN,PN,DN,AN,TN,H
N,2NAN,2NPN,N2ATotal--.. --..-._-. .-_-..-__...-._ ....-.._______________
97182921
97261
252989986963906329872
29829899541010914
211
13006. . . . ....... ...... .............. ....... . . “---_...........-_._.._-......
Tabla 3.- Sourc~ for the cross section data included in
FENDL/A-2.O. [Ref. 5]
EFF-2.4,..ENDF/B-VIJENDL-3. 1JENDL-3.2
JENDL-3.21AJENDL-3.2/M
ACTLLANLADL-3
ADL-3/IFISPRO
SIGECN-MASGAMMASGAMNGAMMA
msEXIFONSIG-ECN
IRDF-90.2ESTIMATE
CRPFENDL/A-l
Total.... ....................-...—-- ... .. ... .. ... ........... . ....... .. . . . . ............
9
515551364
80129
8521149
73411
1753249
122229
411
13006... . . ....... .................. .. .. .............. ... ............. . .... ...... ...... .......
......... ... ..... ... ...
I
Table 4.-
-.. >..-— -— .-.->--------- -
Sources for the cross section data of the important reactionsubidmry of FENDL/A-2.O. [Ref. 5]
.-
... ...... .... . .. ........ .. . ... . . . . . . . . ...... . .. .. ...... .L-__.__.__._.._..__-._..__.,__..,
(1) IRK stands for evaluation originating from the Institute f&Radiumforschung und Kemphysik Vienna.(2) CRP is a product from Research Coordination Programme on the ActivationCross Sections for the Generation of Long-lived Radionuclides of IAEA ~ef.lo].-The rest of selections come from well known and released libraries.
10
.-—----- ---- . . .. -—-.. -
B.-Decay data library FENDIJD-20
The library selected is FENDL/D-2.O.
In the selection of the decay data library the criteria to follow is to takethe one most compatible with the selected activation library (the FENDL/A-2.oin our case). Consequently, the FENDL decay data library (FENDL/D-2.0) isthe logical choice.
. The two main compatibility requirements between the activation andthe decay Iibrary to take into account a= i) all nuclides referred to in theactivation library must have data in the decay library., and ii) the identificationof isomeric states used in both libraries should be identical.
In the selection of the decay data library for FENDL/D-2.0, the choicewas to take directly the EAF-4.1 (EAF_DEC-4.1) decay library.With this choice,based on the fact that FENDL/A-20 is largely based on IMF-4.1, the tworequirements above mentioned have been fulfilled. However, regarding thesecond requirement there are a few cases in which inconsistency ofidentification of isomeric states between the two libraries remain due to theinclusion of theinq.wrhmtreucfionssubfik in FENDL/A-2.o
These inconsistencies, according to the FENDL/D-20 assessment, to beon nuclides of very limited importance for fusion applications so was decidedto let them remain. A new decay library version is expected to be released in anear future by the authors of FENDL &moving these inconsistencies.Otherwise, corrections will be made by ourselves.
FENDL/D-20 contains decay properties (decay ~pe, decay energy, half-Iife, photon yield) for 1875 nuclides and isomers, including ground , first andsecond isomeric states; and it is written in ENDF/B-VI format
The library need to be processed before it can be used by ACAB. Aprogram has been writen to read decay data libraries in ENDF/B-V.O and VIformat for producing two different files , one containig the photon yieldinformation and the other the decay nuclear data, in the format required to beread by ACAB.
11
..... .. ... ...=. —.. . .-..—— -— -—-------
Table 5.-FENDL/D-2.0: Modes of decay and number of ground stateand isomeric state daugthers produced in each mode
719
693
268
1
—
22
3
6
state state
64 2
8 —
—6
—1
— —
— —
—
—
4 —
i .
12
C- Fission yield data library JEF-2.2
The JEF-2.2 fission yield library is selected.
This library contains the energy-dependent fission product yield data forthree different incident neutron energies 0.2S3eV, 0.4 MeV and 14 MeV.Information is given for the independent and cumulative yield coming from 19fissionable nuclides. The fission yield from each of the fissionable nuclides isgiven for around 1450 nuclides.
The fissionable nuclides with fission product yield data in JEF-2.2 arelisted in Table 6. It can be seen that for some of these fissionable nuclides, yielddata are not given for the three energy points, eventhough the fission crosssection is not negligible in some cases for a neutron having the energy of amissing point The sources for the fission yield data included in JEF-2.2 for thenuclides of Table 6, are provided in Table 7.
The format of the library is ENDF-6, and should be processed by theCOLLAPS code (see Section IV) for producing the weighted fission yieldslibraries to be read directly by ACAB.
13
i ...........__+-------------------------------- ..=----.?---——--....
Table6.-FissionablenuclideswithfissionproductyielddatainJEF-2.2.
IJU-24[1 -- Y’ -- I
~ Cm-245 Y Y --
I
II
!
TABLE 7. Sources for neutron-induced fission products yields.
JEF-2.2TAPE 24(FISSIONYIELDS)-...—..-.+- . . . . . . . . ..—— . . . . . . .
......-...-- .....- ....-..-.— .--. ... ...... ...
50-TH-232WIN EVAl#N93 M.JAMESAND RMILLSDIST-JUN93
—JEF-2.2 MATERIAL 9061—NEUTRON-INDUCED FSION PRODUCT’ YIELDS—ENDF-6 FORMAT
ADJLJSIEDINDEPENDENT AND CUMULATIVE YIELD UBRARETERNARY FISSIONAND ~MERICSPLRTING INCLUDEDDESCRIBEDWITHIN REPORTSAEA-TIG-1015, 1018AND 1019.THE WORK wAssFoNsoRED BY THE UKAEA/ BNF PLC AND NUCLEARELECTIUC THLSREMAINS THE JOINT PROPERIY OF THE SPONSO16BUT CAN BElXITUBUTED FREELY. NO LIABfLllY CAN BEACCEPIEDBY THE SFONSORS FORTNE USEyOR MLSUS%OF THIS DATA.
—*-.”* .-**.-.. *..-. -.*e...*..*BD.—
92-U-233WIN EVAL-JUN93 M.JAMESAND RMILWDIST-JUN93
—JEF-22 MATERIAL 9234—NEUTRON-INDUCED FISSIONPRODUCrYfELDS—ENDF-6 FORMAT
ADJUSTEDINDEPENDENT AND CUMULAITVE YIELD UBRARESTERNARY FISSIONAND ISOMERICSPL.ITTU4GINCLUDEDDESCRIBEDWITHIN REPORTSAEA-TltHO15, 1018AND 1019.THiS WORK WAS SPONSORED BY THE UKAU BNF PU2 AND NUCLEARELECTRK TNIS REMAINS THE JOINT PROPERTY OF THE SPONSORSBUT CAN BEDISTRIBUTEDFREELY. NO UABIUTY CAN BEACCEPTEDBY THE SIWNSORS FORTHE US&OR MISUSIZ OF THS DATA.
—-***--A..-*...*—..-—*—.**
92-U -234 WIN EVAL-JUN93 M.JAME5AND RMll&5DfsT-JuN93
—JEF-22 MATERIAL ?237_NEuTRoN-~Du~ F~ON pRoDu~~
—ENDF-6 FORMAT
~ [NDEFENDENT AND CUMULATIVE YIELD UBIURIBTERNARY F195fONAND lSOMEMCSPUITING INCLUDED~BED Wm+IN REPOKIS AEA-B1015, 1028AND 1019.TluswoRKwwsFoNmRED BY THE UKAE& BNF PLC AND NUCLEARELECTRIC THIS REMAINS TNEJOINT PROPERIY OF THE SPOqBUT CAN BEDEIRIBUTED FREELY. NO UA~ CAN BEACCEPIEDBY THE SPONSO16 FORTHE q OR MISUSE OF THE DATA.
.——...*...-—.--.** ——-—
92-u-z%WIN EVAL-JUN93 M.JAMESAND RMILISDIST-JUN93
—JEI-22 MATERIAL 9240—NEUTRON-INDUCED ~ION PRODUCT YDIDS—ENDF4 FORMAT
ADJUSIED INDEPENDENT AND CUMULA17VE YIELD UBRARIFSTERNARY FISHDN AND ISOMEIUCSPUTTING INCLUDEDDSCRIBED WITHIN REPORIS AEA-TI&-1015, 1018AND 1019.TNIS WORK WAS SPONSORED BYTHE UKAEI% BNF PLC AND NUCLEARELECIRK THIS REMAINS THE JOINT PROPER7Y OF TNESPOIWO=BUT CAN BEDHITUBUTED -Y. NO LIABILITY CAN BEACCSPTEDBYTHESPONSO% FORTHE Q OR MISUSE OF TH!S DATA.
15
Table7 continued*........**..*..**..**.**....*.....****.....------
92-U-236WIN EVALJUN93 M.JAMESAND RMIUSDIST-JUN93
—JEF-2.2 MATERIAL 9243—NEUTRON-INDUCED FISSIONPRODUCT YIELDS—ENDF4 FORMAT
ADJUSIZD INDEPENDENT AND CUMULATIVE YIELD UBRARIESTERNARY FISSIONAND lSOMERICSPLI’ITING INCLUDEDDSCIUBED WITHIN REPORIS AEA-TRS-1015,10)8 AND 1019.T1-WWORK WAS SPONSORED BY TNE UKAE& BNF PIX AND NUCLEARELECITUC THIS REMAINS TNEJOINT PROPERTY OF TNESPONSOIZSBUT CAN BEDISTRIBUTEDFREELY. NO LIABILITY CAN BEACCEPTEDBY T1-lESlKX4SORSFORTHE m OR MiSUS~ OF THIS DATA.
.. ..—..-...........a. -..e . . . ..b”w..e.m-.b”w.
92-U-233WIN EVAbJUN93 M.JA~ AND RMILISDIST-JUN93
—JE&2.2 MATERIAL 9249—NEUTRON-INDUCED FISSIONPRODUCT YIELDS—ENDF4 FORMAT
ADJUSTEDINDEPENDENT AND CUMULAmVE YIELD LIBIURIF5TERNARY FISSIONAND lSOMERICSPLITTING INCLUDEDD=BED WITWN REPORTSAEA-TRS101S, 1018AND 1019.THIS WORK WAS SPONSORED BY THE UKAE& BNF PLC AND NUCLEARELECTRIC Ti-HSREMAINS THE JOINT PROPERTY OF TNESPONSORSBUT CAN BEDISTRIBUTEDFREELY. NO UABILITY CAN BEACCEPTEDBYIHE SPONSORS FORTHE USU OR MfS~ OF TH!S DATA.
*....-*.-—— —-..
93-NP-237WIN EVALJUN93 M.JAM= AND RMIU5DJST-JUN93
—JEF-2-2 MATERIAL 9346—NEUTRON-INDUCED FISSIONPRODUCT YIELtX—ENDF4 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD UBRARI~TERNARY F=ION AND ISOMERICSPUTTING INCLUDEDDECIUBED WITHIN REPORTSAwi-ms)m5, lm8 AND lm9.THiSWORKWASSPONSORED BY'TXEUK.AEA. BNFPJKANDNUCL&iRELECTRIC THIS REMAINS THE JOINT PROPERIYOFTHESPONSORSWT’CAN BEDiSIWBUTED FREELY. NO UABIUTYCAN BEACCEPTEDBY THE SPON93RS FORTHE USaOR MISUS50F TH!SDATA.
●✎✎�✍☛☛☛✎�✎✎ ��
93NP-23B WIN EVAL-JUN93M.JAMESAND RMILISDIST-JUN93
—JEW-2 MATERIAL 9349—NEUTRON-INDUCED F15610NPRODUCT YIELIX—ENDF-6 FORMAT
ADJUSI’ED INDEPENDENT AND CUMULAITVE YIELD LIBRARIESTERNARY F=ON AND JSOMERiCSPLllTING INCLUDEDDBCRIBED WITHIN REPORTSAEA-TRS-1015,1018AND 1019.TNJSWORK WAS SPONSORED BYTHE UKAEAc BNF PLC AND NUCLEARELECTRIC THIS REMAINS THE JOINT PROPERTY OF ‘IHSSPONSORSBUTCAN BEDISTRIBUTEDFREBLY. NO LIABIUTY CAN BEACCEPTEDBYTNESPONSORS FOR7?IE USli OR MIS- OF THE DATA.
.
!........
Table7 coatinucd**.**-*-~*.** ....~**-***.***..**. H*......*.......****
94-PU-238WIN EVALJUN93 M.JAMESAND R.MILLSDIST-JUN93
—JEF-2.2 MATERlAL9437—NEUTRON-INDUCED FISSION PRODUCT YIELDS
—ENDF-6 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD LiBRARJ~TERNARY FtSSIONAND M3MERIC SPLITllNG INCLUDEDDFSCRIBEDWITHIN REPORTSAEA-TT?SI015, 1018AND 1019.T?m- wAs sponsored BY TNE UKAEA, llNF PLC AND NUCLEARELECTRK TNIS REMAINS THE JOINT PROPERTY OF THE SPONSOl?sBUT CAN BEDISTRIBUTEDFREELY. NO LIABILITY UN BEACCEPTEDBY THE SPONSORS FORTNE US~ OR MISUSE.,OF THIS DATA.
.-—-- .. .....-..-.- ....— -—..-..
94-PU-239WIN EVALJUN93 M.JAMESAND R.MILLSDJST-JUN93
—JEF-22 MATERIAL 9440—NEUTRON-INDUCED FtSION PRODUCT YIELDS—ENDF4 FORMAT
ADJUSIED INDEPENDENT AND CUMULATIVE YIELD UBIURIETERNARY FSION AND ~MERIC SPLtTTING INCLUDEDDHXIBED WITHIN REPORTSAEA-TRS1015, 1018AND 1019.THE WORK WAS Sponsored BY TNE UIQUM. BNF PLC AND NUCLEARELKIRIC THIS REMAINS THE JOINT PROPERTY OF THESPONSORSBUT CAN BEDISTRIBUTEDFREELY. NO LtABILllY CAN BEACCEPTEDBYTHE SPONSORS FORTHE USE OR MISUSE.OF TNIS DATA.
.ti-**.**-mti.* . . . . ..*...* .*ti**ti.-***.* .***** e*.**
94-PU-240tiN EvAL-Jm93 M.JAM= AND R.MILLSDIST-JUN93
—JEF-2.2 MATERIAL9443—NEUTRON-INDUCED FISS1ONPRODUCT YIELDS—ENDF-6 FORMAT
ADJUSTED INDEPENDENT AND CUMULATIVE YIELD LIBRARI~TERNARY FESION AND EOMERICSPLtlTING INCLUDEDD15CRIBEDWITNIN ~ AEA-T’S1015, 1028AND 1019.THIswORlcwAssFONsORm BYTWEUKAE&BNF -ANDNUCLEARELECITUC THM REMAINS TT-IEJOINTPROPERIY OF TFIESPOmBUT CAN BED~IBUTED FREELY. NO LiABILITY CAN BEACCEPTEDBY THESPONSORS FORTNE USa OR M- OF THIS DATA.
5M-PU-241WIN EVALJUN93 M.JAMESAND RMILISIXST-JUN93
—JEF-22 MATERIAL 9446—NEUTRON-INDUCED FiSSION PRODUCT YIELIX---ENDF.6 FORMAT
ADJUSTED INDEPENDENT AND C2JMULATlVE YIELD LtBRA~TERNARY FISION AND lSOMERICSPLITITNG INCLUDEDDH3UBED WITHIN REPOR’tSAEA-TRS-1015,1018AND 1019.‘TtstswoRKwAssFONsORm BYTHE U~EA, BNF PLC AND NUCLEARELECTRIC THIS REhlAINST1-lEJOINT PROPERIY 0FT14ESPONS01&3BUT CAN BEDISTRIBUTEDFREELY. NO LIABILITY CAN BEACCEPTEDBY THE SPONSOI& FORTNE -OR MISUSE OF TNIS DATA.
17
I .- .-. .
. ... .... ... .. . . . ... .
Table7 continued... . . .........................**..*m*-*. ●...**H*●*..
94-PU-242WIN EVALJUN93 M.JAMFS AND RMILISDIST-]UN93
—JEF-2-2 MATERIAL9449—NEUTRON-INDUCED FISSION PRODUCT Y[ELC5-—ENDF-6 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD UBRARIESTERNARY FEHON AND lSOMERICSPLITTING INCLUDEDD13XIBED WtTHIN REPOKIS AEA-TRS-1015,1018AND 1029.THIS WORK WAS SPONSORED BY THE UKAE& BNF PLC AND NUCLEARELECTRIC. THIS REMAINS THE JOiNT PROPERTY OF THESPONSOwBUTCAN BElWlltIBUTED FREELY. NO LIABILITY CAN BEACCEIIEDBY TNESPONSORS FORTHE w OR MISUSE OF TNIS DATA.
.....a--.~..*- . ..... .. ....—....-
9SAM-241 WIN EVAL-JUN93 M.JAME AND RMILWDIST-JUN93 930702
—JEF-2.2 MATERIAL 9543—NEUTRON-INDUCED FISON PRODUCT YIELC5—ENDF-6 FORMATADJLE71XDINDEPENDENT AND CUMULATIVE YIELD LIBRARJ~TERNARY FISSIONAND EOMERIC SPUTTINC INCLUDEDD=BED WITHIN REPORIS AEA-lTLS-1015,1018AND 1019.THIS WORK WAS SPONSORED BY THE UKAE& BNF PM AND NUCLEARELECTRIC THIS REMAIN5 THE JOINT PROPERN OF TTiESPONSO~BUTCAN BEDiSiRIBUTED FREELY. NO LIABILITY CAN BEACCEPTEDBY THE SPONSORS FORTHE USL OR MISW OF TFUSDATA.
“**..*-* **.*..-.. *****... -**-* *-*-—.*”---
%AM-242MWIN EVAL-JUN93 M.JAME5AND RMILISDIsr-JuN93
—JEF-2.2 MATERIAL 9547—NEUTRON-INDUCED FISS1ONPRODUCT YIELDS—ENDF4i FORMAT
LISOS13T01 RAF CULHAM 4/11/94ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD LIBRARl~TERNARY FISSIONAND ISOMERICSPLITTING INCLUDEDDESCRiBEDWITHIN REPORTSAEA-TRS-1015,1018AND 1019.THIS WORK WAS SPONSORED BY T14EUKAE& BNF PLC AND NUCLEARELECTRIC. TN!5 REMAINS THE JOINT PROPERTY OFllfE~BUTCAN BEDISTRIBUTEDFREELY. NO LIABILllY CAN BEA(XEPTEDBYTHE.5FONSORSFORTHE US~ OR MISUS&OF TliS DATA.
——...———..
9SAM-243 WIN EVALJUN93 hLJAMESAND RMILISD15LJUN93
—JEF-2.2 MATERIAL 9549—NEUTRON-INDUCED FISSIONPRODUCT YCELCS—ENDF-6 FORMAT
ADJU!SED INDEPENDENT AND CUMULATIVE YIELD LCBRARI=TERNARY FISSIONAND EOMER!C SPLITTING INCLUDEDD-ED WITHIN REPORIS AEA-TTS1OI5, 1018AND 1019.THIS WORK WAS SPONSORED BY THE UKAE& BNF PLC AND NUCLEARELECTRIC. THIS REMAINS TNE JOINT PROPERTY OF TNE~BUT CAN BEDISTRIBUTEDFREELY. NO UABILITY CAN BEACCEPTEDBYTHE SPONSORS FORTHE USE OR MISUS50F TWS DATA.
18
.............-- ...—.. .-—-----.-.—.- —-=. --...
Table7 continued
*..**..* **+***..* ....**.**.**.. .... . .... .... ..... ... .
%CM-243 WIN EVALJUN93 M.JAMESAND RMILISDIS’T-JUN93
—JEF-2.2 MATERIAL %40—NEUTRON-INDUCED FISSION PRODUCT YIELDS—ENDF4 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD IJBRARIESTERNARY FEWON AND ISOMERICSPLITTING lNCLUDEDIXXRIBED WITHIN REKXUS AEA-TRSL1OI5,10i8 AND 1019.TNIS WORK WASSPONSORED BY THE UKAE& BNF PIK AND NUCLEARELKTRiC THS REMAINSTNE JOINT PROPERTY OF THE SPONSORSBUT CAN BEDISEIUBUTHl FREELY. NO LIABILIIY CAN BEACCEPTEDBY TNESPONSOIG FOR TNE m OR MISUSE OF TlitS DATA.
%-CM-244 WIN EVALJUN93 M.JAME5AND RMILEDIST-JUN93 930702
—JEF-2.2 MATERIAL 9643—NEUTRON-INDUCED FISION PRODLKT YIELC6—ENDF45 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD UBRARt~TERNARY FISION AND lSObAEIUCSPLITTING INCLUDEDDESCRJBEDWITNIN REPORTSAEA-TRS1015, 1018AND 1019.THIS WORK WAS SPONSORED BY THE UKAEA, BNF PLC AND NUCLEARELEfZRIC THIS REMAINS THE JOW’T PROPERN OF THE SPONSORSBUT CAN BEDtSTRIBUTEDFREELY. NO LIABILITY CAN BEACCEPTEDBY THE SPONSORS FOR THE USE,OR MISUS13OF THIS DATA.
.-.G..”*—-*”***** **-.*-—***
96-CM-245WIN EVALJUN93 M.JAMFSAND RMILISDEIT-JU.N93
—JEF-2.2 MATERIAL %46—NEUTRON-INDUCED FISSION PRODUCT YIELDS—ENDF-6 FORMAT
ADJUSTEDINDEPENDENT AND CUMULATIVE YIELD LJBRARHTERNARY FISION AND LSOMERICSFWTIYNG INCLUDEDDESCRIBEDWITHIN REFORIS ti-mlms, ma AND m’19.llilSWORKWASSPONSORED BY THE UKAE&BNFPLCANDNUCIXAR~ THrsREMAINsT’mJoINTPROPElm oFTHEsPoNsOmBUTCANBE~~FREBLY. NOLlA61LiTYCANBEA~BYTliEWONSORSFORIHE~ ORMISLISEOFTliES DATA.
. ..... C—-- . . .. . ,.. .— . . . . . . . . . . . . . . . . .
HI. Comparison between results based on different cross-sectiondata libraries: FEND1/A-20, EAF-41, and EAF-3.1.
This section is primarily intended to show how results based onFENDL/A-2.0, the newest activation library, compare with those based onsome other earlier important libraries such as EAF-3.111 and EM-4.1. We haveselected the EAF-4.1 for comparison purposes because this library is the basicone for FENDL/A-ZO, and in fac6 there are differences between both for crosssections of only= 235 reactions out of 13006. As far as EAF-3.1, we show resultsbased on this library, although it is the former version of EAIW.1, for tworeasons: i) EAF-3.1 can be considered as one of the most compIete activationlibraries up to 1996, just when the EAF-4.1 started to be used, and then resulIsbased on EAF-3.1 are a good indication of the state-of-art on activation studiesbefore that year, and ii) EAF-3.1 is the library used in the former version ofACAB (ACAB- 2.0).
h the exercice performed here we compute the concentration limits(CL’s) corresponding to handsan recyclin~ remote recycling and shallow landburial (SLB) for each of the natural elements from H to B~ using FENDL/A-2.0, EAF-4.1 and EAF-3.1.
The neutron environment for this exercice is taken12from the midplaneregion of the first structural wall (FSW) of the HYLIFE-I.P reactor vessel. Inthis zone, the most-neutron exposed portion of the vessel structure, the fluxintensity is 1.29 x 10*S cm-2 s-l, assuming a continuous irradiation of 30 yr(corresponding to the desirable FSW life time) and a 75% capacity factor. The
... average neutron energy is 0.38 MeV.
In defining CL’s for recycling two criteria are considered: hands-onrecycling will be acceptable when the contact dose rate does not exceed 25@v/h at 100 yr cooling and remoterecyclingwhen the dose rate is kept below
\ 10 mSv/h within 50 yr cooling. The CL’s on each of the elemenfs are calculatdby assuming the element to be placed in a non-active matrix of iron. In rankingthe acceptability of elements for SLB we have adopted the U.S. class C was~criteria (regulatory guide 10CFR61) using as specific activity knits (SAL’s inCi/ms) those calculated by Fetter et a114.The concentration limit for SLB, i.e.,that for which WDR=l, is computed assuming the element to be present in anon active matrix of a material with densily that of iron (7.87 g cm~). Limits onelements placed in a matrix of different density, D= can be obtained by
,. multiplying the limits computed in this Section by the factor D~/7.87. TheSLB-concentration limits are calculated for shutdown after 30 yr operation.
The concentrations limits of those elements restricted for the consideredwaste management criteria have been compared in Table 8 (for SLB-concentration limik), Table 9 (for remote recycling CL’s), and Table 10 (forhand-on recycling CL’s). In this Tables, elements are listed in decreasing orderof absolute Relative Differences (the definition of the RD index is given at thebottom of the Tables) between EAF-3.1 and FENDL/A-ZO. .
20
When comparing EAF-3.1 versus FENDL/A-2.O we find that most of theelements present negative RD. These differences are very significant for a greatnumber of elements, and so their radiological impact is very conservativelyassessed if EAF-3.1 is used. This explains that in earlier works, proposed lowactivation (LA) elements such as Ta, or W, were assessed as undesirable evenas minor constituent elements in IFE environments; and impurities such as Agwere considered very critical.
Only a few elements present positive relative differences. Thesedifferences for SLB concentration limits, except for Co (RD=O.65), are neverhigher than 0.3. For recycling the highest RD is around 0.9 for IW Se, Ni andZn.
When comparing EAF-4.1 with FENDL/A-2.0, we find that for most ofthe elements the differences are negligible. When existin~ the rdativedifferences are in most cases negative. The most important occur for O and N(not limited with FENDL). These elements, when comparing SLB concentrationlimits, exhibit an RD=-O.9.For Ir the difference is also significant (RD=-O.6). Forrecycling the highest difference appears for Ir, with an RD around -0.6. Forpositive RD, and SLB-CL’S, the highest differences are for Al (RD=O.65) and Co(RD=O.38), for remote recycling there is only one significant difference, Zn(RD=l.3), and for hands-on recycling there are two, ‘N (RD=O.95) and Al(RD=O.65).
It can be concluded that i) large differences are observed between someresults obtained using the new data libraries, EAF4.1, FENDL/A-2.0, and aformer one, EAF-3.1, and ii) EAF-4.1 and FENDL/A-2.O provide in generalsimilar results, but for a few elements, significant differences are found.
Finaliy, we show in Table 11 concentrations limits for recycling and SLBcomputed with FENDL/A-20, as well as the dominant radionuclides with acontribution (given in brackets in the Table) higher than 5% to the radiologicalquantity setting the concentration limit for each waste management criteria.
The implications of these results in ranking and selecting elements forLA material compositions attractive for waste management have beendiscussed elsewhemls. Here. the results are presented so that they can be usedto assess how conclusions of earlier works dealing with the activation of theliquid protected FSW of WE reactors (in which LLNL has a lot of experience,such as the case of HYLIFE-11 reactor) are changed when using FENDL/A-2.O.
21
Table 8. Comparison of SLB-concentration limits ( in wtfraction)obtained from EAF-3.1, EAF-4.1, and FENDIYA-2.O.
ELEMENT
1AwRE0sRHHFPTIRCDLUAGYBcoTBDYEUGOERSMNDHONPOSNK
TMo
NEZRCAMOCuALARBI
CsXEGERUKRASCLNBNI
TESEIBR
EAF-3.1
CL RD*5.55E-05 -0.9913.02E-052.33E-055.70E-051.44E-022.65E-046.00E-013.14E-028.04E-041.1 3E-03
8.58E-051.96E-021.61E-011.84E-062.95E-062.73E-062.08E-061.03E-035.53E561.80E-041.37E-037.15E-044.31 E-(I31.96E-015.14E-034.47E-012.22E+O01.32E+O01.02E-034.23E-011.30E-056.60E-012. IOE-023.32E-029.83E-051.06E-IN
1.55E-011.26E-014.99E-055.86E-023.39E-033.58E-046.99E-073.37E-015.51 E-021.56E-033.47E-01
-0.990-0.990-0.9880.971-0.970-0.9574.940-0.933-0.908-0.885-0.7740.649-0.619-0.619-0.618-0.617+.61 5-0.614-0.605-0.601-0.4720.471-0.441-0.423-0.334-0.3190.2800.191-0.1560.138-0.1340.114-0.102-0.101-0.064
0.0500.0480.0360.018-0.0170.0110.010-0.009-0.0064m06-0.003
2.23E-03 0.000
W-4.1
CL RD5.1 6E-03 -0.1482.56E-031.87E-033.14E-035. 14E-038.66E-037.61E+O02.00E-011.15E-021.24E-026.65E-048.75E-021.35E4N4.82E-067.73E-067.llE-065.42E-06
Z68E-031.42E-05
4.47E-043.31 E-037.53E-042.04E-033.51E-013.73E-036.75E-014.37E-011.05E-018.56E-043.49E-011.14E-059.04E-013.11 E-023.69E-029-82E-051.15E-01
1.48E-011.20E-01
-0.187-0.218-0.358-0296-0.022-0.4504).619-0.0410.006
-0.107O.oos0.3790.0000.000-0.004-0.0020.001-0.007-0.019-0.037-0.444-0.3030.000-0.5820.006-0.866-0.8980.000-0.305-0.0010.1860.6480.000-0.102-0.0010.0000.000
4.80E-055.76E-023.45E-033.53E-046.93E-073.42E-015.55E-021.57E-033.48E-01
O.0000.0000.000-0.0010.0010.0060.0000.0000.000
2.23E-03 0.000
‘ENDUA-2.
CL6.OSE-033.18E-032.39E-034.90E-037.30E-038.86E-031.38E+oI
5.24E-011.20E-02123E-027.44E-048.68E-029.78E-024.82E-067.73E-067.14E-065.42E-062.68E-031.43E-054.56E-043.44E-031.35E-032.93E-033.51 E-018.91 E-o36.71E-013.26E+O01.03E+o08.56E-045.02E-011.14E-057.62E-011.89E-02
3.69E-021.09E-041.15E-011.48E-011.20E-014.81 E-055.76E-023.45E-033.54E-046.93E-073.40E-015.55E-021.57E-033.48E-012.23E-03
. RD. (Results for a paticular activation library- Results for a referencelibrary)/(Reference library results).
. Reference library FENDUA-2.O
i
22
............ .. .. ..... ...... .. . . . ... ... ...... . .. ......
Table 9. Comparison of remote recycIing concentration limits(in wt fraction) obtained from EAF-3.1, EAF-4.1, andFENDL/A-2.o.
ELEMENT
TAwRE0st-lFLUZNlRcoRHSEAGN(BRYBKRTBDYERGORBHOEUPOIfluTESNCuBIMOSMCs8AXEcoCENDNBMNFEPR
EAF-3.1
CL RD*9.39E-04 -0.9915.12E-043.95E-049.63E-044.52E-031.99E-021.47E+O05.28E-011.66E-033.04E-028.58E-021.81E-045.19E-041.99E-033.69E-011.06E-035.44E-058.73E-053.06E-026.05E-051.65E-014.07E-027.71E-058.70E-032.14E-018.91E-023.19E-013.65E412.72E-031.56E-045.09E-022.25E-059.08E-054.30E-031.55E-043.23E-066.18E-014.74E-051.93E-051.85E-012.66E-034.67E-01
-0.980-0.990-0.988-0.979-0.9420.937-0.935-0.9280.9200.907-0.8840.6800.876-0.8370.739-0.619-0.619-0.614-0.6090.608-0.600-0.593‘0.417-0.3870.234-0.201-0.153-0.147-0.134-0.116-0.098-0.082-0.0730.044-0.0160.010-0.0100.0090.0070.0020.000
EAF-4.1
CL RD8.73E-02 -0.1484.37E-023.16E-025.23E-022.08E-013.45E-011.76E+O03.27E+O02.22E-021.llE-024.50E-021.40E-033.07E-041.06E-032.28E+O06.07E-041.43E-042.29E-047.94E-021.53E-041.02E-019.80E-021.83E-044.29E-033.50E-015.46E-023.99E-014.30E-013.1OE-031.87E-046.09E-022.48E-059.88E-053.72E-031.49E-043.29E-066.1OE-O14.79E-051.91E-o51.83E-012.65E-034.66E-01
-0.187-0.218-0.352-0.0420.0001.317-0.588-0.037-0.3020.000-0.1060.1120.0000.0050.000Q.0000.0000.001-0.0130.000-0.037-0.034-0.3010.000-0.244-0.0010.000-0.0300.0390.059-0.0040.000-0.1990.0000.001-0.003-0.0010.001-0.0010.0000.000
FE/JDu&2.c
CL1.03E-015.36E-024.04E-028.06E-022.18E-013.45E-017.59E-018.17E+o02.31E-021.58E-024.50E-021.56E-032.76E-041.06E-032.27E+o06.07E-041.43E-042.29E-047.93E-021.55E-041,02E-011.02E-011.90E-046.14E-033.50E-017.22E-023.99E-014.31E-013.19E-031.80E-045.75E-022.50E-059.89E-054.64E-031.49E-043.28E-066.12E-014.79E-051.91E-051.83E-012.85E-034.66E-01
. RD: (Results for a paticular activation library- Results for a referencelibrary)l(Reference library results). -
● Reference library FENDLIA-2.O
Table 10. Comparison of hands-on recycling concentration limits
(in wt fraction) obtained from EAF-3.1, EAF-4.1, andFENDUA-2.O.
ELEMENT
TAwRE0sHFPTIRLUCDCARHSEAGNIYBI(R8ROYTBERGDRBHOSNEUTl
SMPDSc
ITMPBRUZRSBuND-I-ESRCuK
L61
6AALCsXECEcoNBMNPRFE
EAF-3.1
CL RO”2.71 E-06 -0.9911.48E-061.14E-062.78E-061.30E-052.93E-021.53E-035.71E-o54.61E-061.04E-028.33E-055.40E-034.W3E-079.23E-041.05E-036.6SE-051.04E-042.25E-071.40E-077.66E-051.56E-071.04E-021.05E-046.24E-032.00E-073.26E-013.56E-072.47E-058.29E-02223E-033.36E-022.22E-022.39E-043.26E-021.22E-011.95E-024.19E-063.21E-03231E-014.64E-037SOE-02
-0.990-0.990-0.9684.977-0.957-0.940-0.935-0.932-0.9240.9220.903-0.6650.879-0.8350.7370.725-0.619-0.619-0.614-0.6100.610-0.601-0.598-0.597-0.586-0.5230.4670.3764.374-0.322-0.2740222-0.219-0.2070.1994.192-0.1660.156-0.147-0.141
1.16E-061.28E-041.oIE-042.1 8E-038.44E-07125E-067.56E-025.75G064.63E-063.28E-016.21E-02
-0.134-0.120-0.1190.114-0.0670.0490.027-0.0160.0090.007-0.005
5.09E-03 0.003
EAF-4. 1
CL RD2.52E-04 -0.1481.26E-049. 12E-051.54E015.54E-043.73E-019.76E-038.79E-046.54E-051.51E-013.02E-052.84E-033.81E-065.46E-046.41 E-o33.83E-056.05E-055.69E-073.67E-072.05E-043.96E-076.47E-032.53E-041.55E-024.83E-071.54E+o07. 18E-071.17E-056.03E-C23.55E4?35.OIE-023.18E-E21.48 E-G429E-EZ1.54E-c I1.63E-?i5.07E-053.95E-C31.86E.015.51 E-1238.86E-02
-0.187-0.2184.366-0.037-0.453-0.619o.m2‘0.0400.110-0.3030.000-0.1070.112O.owO.0000.0000.0000.0000.001-0.0110.000-0.037-0.001-0.0280.953-0.036-0.3030.0000.0000.0060.040-0.2430.028-0.001-0.002-0.0220.000-0.0654.0300.014
1.39E-061.54E-@G6.43E-05323E-039.04E-071.19E-067.06E-025.85E-064.78E-063.26E-OI623E-02
0.0400.053-0.4370.6480.0000.000-0.0390.0010.0000.000-0.002
5.06E-03 0.000
‘ENDUA-2.
CL2.96E-041.55E-041.17E-042.39E4M5.75E-046.81E-012.56E-026.77E-046.82E-051.36E-014.33Ea2.64E43427E-064.91 E-046.37E-033.83E-056.05E-055.89E-073.67E-072.04E-044.00E-076.47E-032.62E-041.55E-024.97E-077.87E417.46E-071.66E-056.02E-023.55E-CL34.98E-023.06E-021.96E-044.17E-021.54E-011.63E-025.1 8E-063.95E-031.!39Ea5.66E-038.73E-021.34E-061.46E-041.14E-041.96E-039.05E-071.19E-067.36E-025.84E-064.78E-063.26E-016.24E-025.07E-03
I
● RD: (Results for a paticular activation library- Results for a referencelibrary)l(Reference library results).
. Reference library FENDL/A-Z.O
..
24
. . ...... ... .-....- -----
Table 11. Limits on element concentrations (inwt fraction),and
contribution of dominant radionuclides.
RSCYCUNGmNcsNmA730NL3Mn-s
ELSMS?37 S3.s REMOTEREcYcLe4G
SLs REMGTENANGS4N
mmGoWDYSmCsx!!U
MPQcoFoKRmlBRcomREMowmlER0sm7ANIHI=wAL
SEI
TEFECuYERBSr3LAm?BmTMScFRCEK
CASsSKMNPTnaMASARGEm
NE 64 (loo.) Ne 64 (la)W166M floo.) N0166M (300.)N0366M (62.) NOW6M ( 66.)IW46M ( Sk) yOJ/,z12.0366M ( WNe164u (lea)lWmM ( *7.} EU3S4 ( 91.)”No166t3( 6.)CS127 (loo.) M132 ( 16.) SA1S7M ( 64.)CS137 (166.) SA137M ( w.)S3206 (140.) Uso7 floo.)tilo6M (lOo.f AG106M (66.)TB1S6 ( 7.JNS36W ( 62.) EU3S4 ( es.).FS60 (n.xoes (m.) Cosoom.) ‘AGtWM (W&) AGloeu(ee.)KR*! (loo.) KR Ss (160.)AG106M (67.) AG106M(w.)KRal (6s.) KR 6s (loo.)AG103N (lOR) AGIWM (S1.JCD113M ( S.)
SA1S2 (77.) t3Al~(22.)rA162e (loo.) IR1S2 (loo.)Tc 66 ( 46.) NE ,1 ( 24.} ND 64 ( 7E+)rK162s (loo.) rRle3 (loo.)Tc 66 ( 10.)TC66 ( $s.) m 66 (24.) AG106M( 74.)N4166M (Ioq N0166M (300JWI* (loo.) rR162 (67.]IW166M (s06.) N0166M (160.)IK162S (100.) IR1,62 (160.)MS6 (s4.p4r62 (u.) m 60 (160.)NFW3 ( 72J4R1SS0 ( 27.) TA162 (S6.)S1162 (40.}NF363 (a)rR3m2 ( 7.) HF162f 7.) TA162f 01.)’ml~ 12.)AL24 (lea) AL 26 (160.)SE 73 f360.) KR 6s floo.)n29 (loo.) 0A122 ( 2SJ 0A127M ( 7S.)1126 fwq BA122 ( 22.) BA127M ( 77.)
co 60 (la.)Ma (66.) co 60 (100.)NF162 (66.)
m 6s (1OOJSN121M ( s.pm6 (%.) sNi21M( 8.) SS12S (66.)
W629 000.)
TC 66 (160.J NOM (66.)NF162 ( 66.)
KU3S4 (6WW*S6 (m)
a26 (WAR23 (*a36fss.)ARss(46.) K4ql&]cA43(lQ -
.
co 60 (loo.)
u. 26 (lea)c 14 flee.)
SE 76 (100.)AR36 (66.}SE 79 (360.)
co 60 (loo.)
NE 64 (loo.)Im66u (300.)N6166M( 66.)mtse ( 10.INOWM (66.)N0166M(loo.)SrJ3sq 19.)TS1S6( 12.)NO1* 66.)SA1S7M(6S.)SA127M (30h.)S1207(100.)AG306M(loo.)SU1S4(m).mluf 7.) N6166uf 14.)co 60 (loo.)AGl~ f300.)KR 66 (100.)AGloeu f300.)KRw (m) KR6s (60.)AG106M (66.)@A122 (26.) SA137M (7$.)lr41s2(loo.)N69t (24.)NB64 (~)IR162 (100.)TC66 (26.) AGmsrA(74.)NW66M (loo.)IR163 (loo.)N0166M(loo.)Wm (100.)co 60 (loo.)YAWS ( S6.)IR162 ( 3K)NF162( 7.) TA162(62.) U4192(11.)AL 26 (loo.)KR m (loo.)SA127M (66.)SA137N ( 66.)co 40 (300.)co 60 (loo.)NF162 ( 6.) TA163 { 66.)KR 66 (106.)SN321M(66J WI* 7.)sB126Mf 26.)SA137M (m.)mw2 (mm)Er207 (16a)NS64 (66.)NF362 ( 6.) TA162 (63.)K 42 (W.)EWES ( &)sLr3s4 (s4.)sA137t6( 11.)sutq S.) SU1S4(64.)K40(S3.)K42(~K40(SS.)K42 (14.)SN121M(Et)KR66{s7.)Yw (l&)co@ (100.)m362 (loo.)K 42 (100.)
&[email protected]+11.46E-ot1.osE-047.44s444.s6s-04n.76E-022.63s-02S.76E-027.30E.02S.22c42120s-02
NL2.26E-OS1.14s-053.1SE424.81E-os7L66E-024s0s.023.443Ea&06S-022.40E-016.66fwsW2E421~t.s7E-622.46E-016.SSE42
NL7.6ss-01&.66E-02
NL2.s1Eat
NLs.24E4i
NL&s6E-04e.71E-ol
NLNLNL
S.63E.02S.oss+l
NLNLNLNLNL
2.64E-041.2SE.023.4SE-023.66E-02*aE+*
NL
1s1s-0s1~1.sss44tSwo4226s-042.SOE-OE6.6ss.061.46s-041.60s41.sss-034-*-OS3.26s+6.14s-026.07s441.S6E-021.06s-022X 3!-024.64E+24.04E.02S.7SS-025.26243722E-027.62E-026.66s-021.02s.011.02E-012.76E-042.16s-012.4ss-017.64s.014.so&023.60s-01S.66E.012.8SE-03S.WE.G2
NL1Q2E+14.31E-o3
NLNLNL
1.62E+01NLNL
4.s6s.016.12E-Ql
NLNLNLNL
1.62E-01NLNLNLNLNLNLNL
7%ss.01
Elementsnot reetrkted for SL9andRecyoling criterh: H, He l-f,Be.B.C,O,F,No.Na,Mg,Si,P,S,Tl,V,Cr,Ga,Y,Yb, Au, Hg
25
4.7@E-063.G7E-074.00E-074.67E-07S.S6E-677.46E.07e.06s-071.WE-061.24E.064.27E.06S.18E-06S.S4E-061.66E-os3.62E-oS4.32E-oS&05E-056.62E-051.14E.041.17E-041.46E-041.55E-041.%E-W2.04E-042.2SE-042.62E-042.66s-044.61E-04s.7SE-O.3w77E-041.66E.032.64E.033.65E-033.66E-03S.07E-03s.66E.036.27E.036.47E-031.SSE-021.42E-022.S6E-02%06E+24.*7E*24.66E.026.02E-02624E-02736E-02a72s421.S6E.OIlSE.011.66E-01U36E.OI6.61E-017.67E-ot
NLN1.NLNLNLNL
I .. ... ........ ... ... .. ... ..—..--— —-—.-—.—---.-—— . .... ... ...
IV. Collapse processing code.
COLLAPSE is a utility program that has two major facilities. Firstiy it is used tocondense multigroup cross section libraries down to a single group. When runningCOLLAPSE in this mode (ISFIS=O), that we call hereafter “standard mode”, theneutron fhx is used as a weighting function to produce the l-group energy-averaged(“effective”) cross sections. The neutron spectrum may be input in an arbitrary groupstructure. Secondly, COLLAPS can use fission yield data in conjunction with fissioncross sections and neutron spectrum to compute effective fission yield cross sections,
.qcm When running COLLAPSE in this mode (ISFIS=l),that it will be referred to as“fission mode” hereafter, it is produced a library containing l-group effective crosssections, and other containing l-group effective fission yield cross sections.
When ACAB is going to be run for inventory calculations considering fissionproducts, previously to run it the user must run COLLAPS with the option JSFE3=1,since ACAB need as input the effective fission yield cross section library, such as it isoutput by COLLAPS. When the inventory of fission product is not going to becomputed by ACAB, the user is recommended to use COLLAPS (with the optionISFIS=O), but it is not mandatory, since ACAB can read a library in any groupstructure, provided it is in EAF format
Regarding the operation of COLLAPS in the standard mode, the cross sectionlibraries to be “collapsed” must be in the format used by the European Activation File(E#@). COLLAPSE currently is able to handle cross section libraries in the standardVitamin-J (175 groups), GAM-11 (100 groups), and. TART (175 groups) groupstructures. These group structures are given in Tables 12-14. The ability to deal withlibraries in other. group structures can be easily implemented in COLLAPS. Theneutron spectrum employed to condense the cross section library, if possible, is
}.advised to be in one of those structures. When the neutron spectrum is given in agroup structure different from those listed above, COLLAPSE begins by convertingthe spectrum into one of the standard structures (as specified by the user). After.+conversion is completed, the code condenses the cross section library.
When COLLAPS operates in the fission mode, the quantity to be computed is.the effective fission yield cross section ~. This is defined as the spectrum-averagedneutron cross section for formation of nuclei of type i by fission in the nuclei of type j,and may be expressed as
where,
26
[1]
——-..... ..-—------ ---------.------~- . .. .
!
Yj.i is the probability that a a type-i nuclide will be formed as a fission product byabsortion of a neutron of energy E by a nuclide of type j.
~~jis the microscopic fission cross section of type j nuclei for neutrons of energy E.
6 is the total energy integrated neutron flux.
In computing this quantity some assumptions are made to deal with theinformation f%omJEF-2.2
i) Three energy regions are defined, assuming that independent yield data areconstant in the energy range of each region. The energy ranges for these regions areEQOOkeV (low energy region), 5 MeV>-200 keV (mediumenergy region), and )+5MeV (high energy region). These regions have been selected taking into account thethree energy incidentenergy points for yield data considered in JEF-2.2, that is: y at0.0253 eV, y at 0.4 MeV and Y at 14 MeV. So, these points are assigned to theIow,medium and high energy regions,respectively.
ii) For some of the fissionable nuclides considered in JEF-2.2, yield data are not givenfor all of the three energy points, even though the fission cross section is notnegligible for the neutron having the energy of a missing point To work out thissituation we have assigned to an energy point lacking yield data, the yield data ofthe closer one.
iii) In JEF-2.2 there are 19 fissionable nuclides, while in the activation libraxyFENDL/A-20 there are 61 nuclides having fissioncross sections.COLLAPSallowsto obtain w files for both 19 and 61 nuclides. In obtaining the library of theeffectivefission yield cross sections for the 61 nuclides, the nuclides with no fissionyield data in JEF-2.2, are assumed to have those of the neighbounng nuclide withfission yields available.
COLLAPSE is controlled via the standard input unit (file 5). Unit 2 mustcontain the cross section library to be condensed. COLLAPS write on UNIT 18 theindependent fission yields for the three energy poink, this file is referred tu as theexten&@wn @hi library.This library is not dependent on the weighting neutronspectrum and therefore, it can be used once generated in a previous rum as an inputfile containig the fission Yield information, instead of using the basic fission yieldlibrary,JEF-2.2 (UNIT 17).
Output is automatically written to two files: unit 9 contains the l-group crosssection library in the EAF formak and unit 8 gives the l-group neutron fiux andaverage neutron energy. When runnig COLLAPS in the fission mode, UNIT 96 is
27
i., . .. ... .. ...-. ..-. --. -.—------------ .—-—-— --------- -~~-.----—----------
..-.—..———----... .-—.-.--.’.. - .>--------- .. . . .._o. —----- . . . . . . . .
generated containing the one-group fission yield cross sdions. Also UNIT 18 isgenerated containig the extended library of independent fission yields. This Iibrarycan contain the information for all fissionable nuclides included in JEF-2.2 and/or inthe reaction cross section data library.
The input file is formatted and must contain the following information
card #1: (format is 214)
The first card is used to speci~ the group structure that is used in the crosssection library and for the neutron flux.
~ Parameter Description
2 IESF
1 I-LIB Group structure used in the cross section library1 GAM-11(100 grOUpS)
2 Vitamin-J (175 groups)3 TART (175 groups)
Group structure used for the neutron flux1 GAM-112 Vitamin-J3 TART4 Other (arbitrary)
card #k (FORTRAN free format)
This card is used for reading the information heading the activation cross-section library.
f Parameter Description1 IHE.AD Number of lines heading the cross section
library. This heading lines providegeneral information about the library.
28. .
Card #3 (FORTRAN free format)
This card controls the generation of the effective fission yield cross section library. Ifthe first parameter of this card is O,the rest will not have any effect and can take anyvalue.
2
3
Parameter DescriptionISFIS Indicator for the fission mode operation.
o No effect. The other parameters of this carddon-t have any effd if ISFJS=O.
1 Fission information is processed.
IGEN Indicator for controlling the generation of the “extended”fission yield data library.
o No effect Standard fission mode of operationfor the generation of the effective fission yieldcross section library.
1 -Generation of the “extended” fission yielddata library (UNIX 18) for all fissionablenuclides included in the basic (UNIT 17)fission yield data library.Qneration of UNIT 28, this one contains theextended fission yield data library for allfissionable nuclides included in the reactioncross section data library.After the generation of UNIT 18 and UNIT 28the code STOP. No effective fission yield crosssection library is generated.
Processing of the basic fission yield data library (UNIT 17).
o No effect The code reads UNIT18 (extendedfission yield data).
1 Reading and processing of the basic fissionyield data library JEF-2.2.
29
IBEST Selection of the effective yield cross section Iibrary(UNIT 96).
o Effective fission yield data libra~ is generatedfor the fissionable nuclides included in theoriginal fission yield data library (UNIT 17).
1 Effective yield data library is generated for allfissionable nuclides included in the reactioncross section library (UNIT 2).
card #& (FORTRAN free format)
This Card gives the fission yield energy group structure for processing of JEF-2.2 Independent yield data are assumed to be constant in each energy group.
& Parameter Description1 EB Energy boundaries (eV) of the energy regions where
independent yield data are assumed to be constantThe energy boundaries are given in order of decreasingenergy [2].The group boundaries corresponding to each energygroup are 14 Mev -EB(l),EB(l)-EB(2) y EB(2)-0.0253MevThe values suggeskd are 5 Mev for EB(l) and 200 Kevfor EB(2).
card #5: (format is 214)
This card gives the number of groups” used in the neutron spectrum and theutits of tb.eneutin flux.
i><,g - Parameter1 NGROUP
FF
DescriptionThe absolute value of NGROUP is the number of neutrongroups of the neutron spectrumIf NGROUP C O,the neutron flux group structure is givenin order of decreasing energy.If NGROUP >0, the neutron flux group structure is givenin order of increasing energy.
Units used for the neutron flux descriptiono Total scalar flux [n/cm~s]1 Flux density [n/cm+-MeVl
30
. .. .. ...... .. ....
Card #6 (format is 6E12.5)
Card #6 will only appear if IESF = 4 indicating that a group structure other thanGAM-IL Vitamin-J, or TART will be used to specify the neutron flux.
g Parameter Descri@ion1 a Energy boundaries of the group structure used for the
neutron flux. The order of the energy boundaries is givenby the sign of NGROUP.[NGROUP+l].
.
Card #Z (format is 6E12.5)
When IESF# 4, card #6 will not appear, and thus, card #7 will immediatelyfollow card #5.& Parameter Description1 FT Flux levels within each energy group. UNh of the flux
are given by FF and order (ascending or descendingenergy) is given by the sign of NGROUP.[ABS(NGROUP)].
Example input fihx
2316
101 15.E+062.E+05
-1750MOOOOE+OO1.0000OE+OO1.0000OE+OOMOOOOE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OOMIOOOOE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OOMOOOOE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OOMOOOOE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO
31
I . . . . .. --— ------- . . . . . ..- . ..-. --. -—.-—----. . . . .. . ..-.~... .
1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OOI.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO1.0000OE+OO
In the above example, the neutron flux is given in TART 175-group formatwhile the activation cross section are given in VITAMIN 175-group format Thenumber 16 means that there are 16 heading lines in FENDL-A/2.O. The parameters ofthe next card are ISFW1 (meaning that ACAB is going to run in “fissionmode’’),IGEN=O( so this is a “standard fission mode of operation”, and the effectivefission yields cross section library is generated),ISOCA=l ( in this case the the basicfission yields data Iibrary JEF-2.2 is processed) and IBEST=l ( the effective fissionyield data library is generated for all fissionable nuclides contained in the activationlibrary). The next card shows the two values suggested in card #4 for the energieslimiting the three regions are considered in fission yield processing.The negative signin front of the 175 in the following card, indicates that the fluxes will follow in orderof descending energy. The fluxes are given in units of n/cm~s as indicated by FF = O.Because IESF # 4, card #6 is omitted, and the 175 fluxes immediately follow card #5.
.
.—
—
.
32.
i
Table 12. Energy group boundaries fortllc Vitamin-J 175-groupstructure. The upper energy for group #I is 19.6 MeV.
Tabla13. Energy group boundaries for the GAM-11 100-group
structure. The upper energy of group #l is 14.9 MeV.
EGrou # ~ (MeV)
1 135E+41
2 1.22E+(N
3 1.llEi4)l
4 1.00E+O1
> ——. . # Group # I & (Mev)36 4 (MF4)I II 71 I 4S4E-04-. I ----- --
1—— ___
% 334E-
IS19-05E+410
l=+==6 8.19E+LW)
7 7.41E+tll
.8 6.70E+@l
.9 .6.Q7W0
10 5.49E+W
41 I Z47E411 n 76 l“lS
.,
,.,
..““%RE%46 I HOE-01 n 31 I 3.73E-05
47 i 136E-01 82 J .Mw1548 I 1.23E-01 U 83 226E-05
‘ B;’
—. I
so 1 M5E42 H * 137E+3574E-02r 86 M7E-05
52 I 525?302 u 87 .832)306
E14E53 I 4J.)9E-02 m’ 6.48E-0654 3.18E-02 89 5.q4E416
48E-02 h 90 I 3-93E-06----
ii ;4._1, I
-.. .
56 1.93E-02 91 3.0(
22 1.65E+O0
23 150E+O024 lKWOO
25 122E+O0
26 L1lE+OO
-. !
a
91._ __ ,, .,- , ,.-.––-59 I ‘:- ~60 I 7.1OE-O3 H 95 I 1.13E-0661 %53E-03 % 8.76E4)7
la=.<.
27 1.00E~
28 9.07M1
.:29 S21E-01
30 7.43E-01
31 6.72E-01
62 I 43m03 ! 97 6.83E47
63 3.35s03 98 532E4)7
64 2.61E-03 I 99. 4.14E-07
6.5 203E-03 100 5.1OE49.. .
E32 6.08E41
33 550E-01
34 -L98E-01
35 4SOE-01 70 I 5.83E-04 1!
.,
34
\
——-
Table 14. Energy group boundaries for the TART 175-group structure.The upper energy for group #175 is 20.0 MeV.
35
V. Data libraries for ACAB.
ACAB makes use of six different data libraries. These libraries providedata corresponding to:
1) decay data (UNIT 3);2) photon production (UNIT 33);3) neutron reaction cross sections (UNIT4);4) mass attenuation coefficients (UNIT 68);5) ftdecay data (UNIT 27); and6) specific activity Iimits for Waste Disposal Ratings
(UNIT55).
Decav library
Only isotopes that.are included in the dway library may be generated inACAB calculations. The ciwrent decay data’ library is based on the ~NDL/D-20 !ibra~~ taken from the International Atomic Energy Agency, IAEA. Modesof d~ay considered “inthe library are listd in table 5. The decay library hasdata for, 2A isomeric states, including transitions from the 2A to la isomericstates. Also possible are ~ and ~- transitions to excited states. A utility programis used to read the decay library, and a file with information for naturalisotopic abundances taken (Nuclear Wallet Cards,July 1995)16in order to createthe library for use with ACAB, Unit 3. This library has a title card which isfollowed by two lines of data for each isotope. These lines are formatted andcontain the following information .,
Line #l.
f12
3
456
(format is 14, Ill, 13, 4X, 6E1O.3)
Parameter DescriptionNLB Library identifier.NUCL Isotope identifier. (= Z x.liY + A x 10 + M).
Z = atomic numbeq A = mass number; M ==isomericstate (Ofor ground state, 1 for 1~ isomer, 2 for 2Aisomer).
Iu UNts of the half-life1 Seconds
“2 Minutes3 Hours
.4 Days5 Years6 Stable
“7 1(P years8 1(F”years9 1P years
THALF Half-life.FBx Fraction of ~- transitions to an excited state.FPEC Fraction of transitions by positron emission and
36
7
89
Line #2
456.78.,
electron capture.FPECX Fraction of (3+and electron capture transitions that
result in a product in an excited state.FA Fraction of a transitions.FIT Fraction of isomeric transitions to the ground state.
(format is 14, 5X, 4E1O.3,1E11.4,2E1O.3)
Parameter DescriptionNLB Library identifier.FB Fraction of@ transitions.FSF Fraction of transitions from the 2~ to 1s’isomeric
state.Fraction of (J3+ n) transitions.
&iiEc Average energy of the emitted a + ~ + y.ABUN Natural isotopic abundance.ARCG Maximum’ permissible concen”&ation,ina~ (Ci/ms)..WRCG ‘ Maximum pefinissible conixmtration in,watq
{Ci/ms).
Example
1 771922 1 7.600E+09 0.000E+OO 0.000E+OO 0.000E+OO0.000E+OO 1.000E+OO1 0.000E+OO 0.000E+OO 0.000E+OO 1. 61 OE-O1 0.00 f1E+OO 0.000E+OO0.000E+OO
...
This eximple gives dixay information for l~Ir. It,shows that the,half-lifeis 7.6 x“109seconds ~ 241 yeais, that 100% of the isomeric transitions go to theground state, and that the average energy of a + ~ + y is 0.161 MeV perdisintegration. When maximum permissible concentrations for a givenradionuclide are not available, as they are not for lgW.r,a value of 0.0 Ci/ms isspecified and not used for the BHP computation.
Photon librq
The photon library consists of data from FENDL/D-2.O. A utilityprogram is used to extract the photon information from this Iibrary for use withACAB, Unit 33. The photon library also contains two lines per isotope andcontains the following information
Line #k (format is 13, A4, 13, Al, 4X, 15)
& Parameter Description1 z Atomic number.2 SYMBOL Chemical symbol of the nuclide.3 A Mass number.4 STATE Internal state (blank for ground state, M for
l~isomer, N for 2A isomer).
37
. .
\
..-. ._,_.=... — _-_... ---- . . . . ....-—— -.s-------------- . . . . .. .. . -
5 NR Number of energy/photon intensity points thatfollow.
Line K2 (format is (ENER(N), IIVTS(N), N=l,NR) 6E11.4)
& Parameter Description1 ENER Photon energy (MeV).2 Number of photons of that energy emitted per
100 disintegrations.
Example
11 ~li 24 69.9800E-01 9.5000E-04 1.3686E+O0 9.9999E+01 2.7540E+O0 9.9944E+012.8700E+O0 2.0000E-04 3.8672E+O0 S.2000E-02 4.2380E+O0 7.5000E-04.
Thisexamplegives 6photonyields for 2zNa.Thedatashows thatnearly:, 100.photonsatl.37 MeV,100photons at275MeVand0.05 photonsat3.87
MeV are emitted per 100 zqNadisintegrations. Photons areproduced at otherenergies but at rates of less than 1 per l& disintegrations.
Cross section libriarv
ACAB currently uses the FENDL/A-20. This library follows theENDF/B format Other libraries currently adapted for use in ACAB are theEAF-4.1 and the EAF_3.1. These libraries are in the 175-group Vitamin-J groupstructure, the 100-group GAM-11 group structure, and the 175-group TARTgroup structure. (See tables 12,13,14).*.
ACAB can be used with any group structure as Iong as the cross sectionsand fluxes use the same structure. When this is not possible, one can use theCOLEAPSE (see section IV) code to generate l-group cross sections and a 1-group flux from an arbitrary group structure and one of the existing versions ofthe cross section library.
ACAB reads the cross section library from unit 4. For each reactiom thereare four lines of formatted data that contain the following information
Line #1: (format is 316, 3X, 13A4)
R Parameter Description1 MAT Nuclide identifier that is composed in the same
manner as NUCLID (see block#4)2 MT Reaction identification number3 MAXG Number of group cross sections
that follow for the MTreaction on the MAT target
38
i .............. -------..
Lines #2 and #3 contain alphanumeric text that provides information about thesource of the cross section data. The format for these lines is A80.
Line #4 (format is 6E11.4)
& Parameter Description1 XSEC Group cross section values in order of decreasing
energy. [MAXG].
Example
2605401030 64 FE 54 (N,P )MN 54 l.ooOO+Oo*JENDL-3.2/A
1.44243E-01 1.78388E-01 1.93273E-01 2. 17498E-01 2.77143E-01 3.05415E-013.32740E-01 3.59740E-01 3.88597E-01 4.20519E-01 4.67806E-01 4.90825E-015. 17509E-01 5.33006E-01 5.38475E-01 5.32787E-01 5.29980E-01 5.29970E-015.29970E-01 5.29969E-01 5.29247E-01 5.25649E-01 5.21871E-01 5. 14627E-015.05856E-01 5.00722E-01 4,99981E-01 4.94351E-01 4.77434E-01 4.51470E-014.20320E-01 3.8597733-01 3.53527E-01 3.01523E-01 2.50248E-01 2.20914E-011.80842E-01 1.50903E-01 1.24257E-01 1.01958E-01 8.28641E-026.59863E-025.57254E-025. 15133E-02 4.98545E-024.7401 OE-O2 4.25914E-023.51 130E-022.66249E-02 1.9351 lE-02 1.40036E-028.98573E-03 5.83579E-03 3.78654E-031.83925E-039. 17771E-047.75506E-04 6.40134E-045. 11356E-04 3.88892E-042.72320E-04 1.08842E-04 1.61658E-070.0000OE+OO
This example contains the cross section data for the ~Fe (up) ~Mnreaction. The first line provides header information that gives the target atom,the reaction number, the number of cross sections that follow, and the reactionname. The second and third lines are used for general/comment information.Beginning with the fourth line, the reaction cross sections are given in order ofdecreasing neutron energy. This reaction is a threshold reactio% cross sectionsare given in 64 groups.
Fission yield cross-section library. .
The one-group fission yields cross-sections are read from Unit %. Foreach fission product the effective fission yield cross sections coming fromevery fissiomble nuclide are given.The information is provided in increasingorder of the Nuclide Identifier ( that is 1000O*Z+1O*A+IS)of the fission product,
Line #k (format is E1l.6)& Parameter Description1 INuc Nuclide identifier
39
.........----=—’--
Line #2 (format is 6E11.6)g Parameter Description1 FE3YI One-group fission yield cross section from every
fissionable nuclide. [19] or [61].
Example:
.5513702 -06
. 10382 OZ-O4
.10381 W-O4
. 561259Z-02
.5322313 -02
.445327E+O0
. 899685&-04
. 13993 BZ*O0
.169664E-02
. 928013E-02
.1442 <8:-01
.499317Z-02
. 10382 OE-O4
. 104441E-O4
. 962220E-05
. 166427E+01
.394384E+O0
. 946324E-05
. 479323E-02
. 700433E-01
.6057 E4E+O0
. 110554E+O1
.393831E-04 .104441E-O4 .356798E 03 .12767$E-06
.232205E-01 .133648E-05 .699734Z-02 .786051L-05
.347454E-02 .524137E-05 .1E5700E-03 .133186E+01
.299527E-02 .602248E+O0 .320831K-02 .304851E.+01
.708521E+O0 .196313E-02 .173497E+O0 .285659C-03
174368E+O0 -217655E-02 .482195E+O0 .124616E-02
.204057E+O0 .131276E+01 .252521E-01 .273775E+O0
.174465E-03 .384682E-02 .497528E-02 .203873E+01
.187479E+01 -950318E-03 .286936E-01 .192052E+01
.882788E-02 .473461E+O0 .247719E-02 .813901E-01
This example containes the one-group fissionyield cross sections forG-137 coming from all the fissionable nuciides (61) included in FENDL/A-2.O.
Massattenuation coefficientlibrary
Massattenuation coefficients areread fiomUnit68.These havebeenrecompiled and calculatedly Hubble17.These aregivenin35 energy groupsthat range from 1.0- 1.5keVto15-20 MeV.Themass attenuation file containsdatafor40elements withatomicnumbers aslowashydrogen (I)andashighasuranium (92). The mass attenuation coefficients are given inunitsof mZ/kg.
Example:
PB 826.205E-3 5.658E-3 4.972E-3 4.675E-3 4.391E-3 4.272E-34.197E-3 4.234E-3 4.607E-3 5.222E-3 7.103E-3 8.869E-31.248E-2 1.613E-2 2.323E-2 4.026E-2 9.985E-2 2.014E-15.550E-1 2.419E-1 5.020E-1 8.041E-1 1.436E+0 3.032E+08.636E+0 1.116E+1 1.306E+1 2.287E+1 4.672E+1 7.304E+11.251E+2 1.965E+2 1.285E+2 2.356E+2 5.21OE+2
~ decav library
Unit27givesthe averageenergyper &decayandthe fractionofdisinte-grationsthatoccur via&decayforeach isotope. Thisinformation isderivedfromUKDECAY3 andisused tocalculate theBremsstrahlung dose rates.
Example
601404.94750E+04 1.0000OE+OO
This example gives the ~-decay information for l<. The average energyof j3 particles is approximately 49.5 keV and jkiecay occurs for 100% of thedisintegrations.
Specific activity limits are read from Unit 55. These limits are maximumconcentrations allowed in Ci/ ms for the waste to be eligible for shallow landburial. The limits used by ACAB are those calculated by Fetter, Cheng, andMamls.
Example
130260 9.0000 E-2
This example give the specific activity limit for ~Al as 0.09 Ci/ms. Thatis, radioactive waste that contains only ~Al at a concentration of less than 0.09Ci/ms would be eligible for near-surface land disposal as Class C waste.
VI. Input Description
ACAB inputdata is structured in data blocks.Blocks#l,KMW5,#6,#7,#8 andW are read in FIDO fme format and the rest (blocks #4, #10 and #11 are read inFORTRAN free format In the FIDO format blocks, all cards starting with anumber$$accept integer values, and those starting with numlxP require floatingpointvaluesmustend with a “T”.
Comments may be interspersed throughout an ACAB input file. Commentsare denotedby a singlequote(’) in the firstcolumnof any line.
Numbers in [ ] are dimensions of the vector or matrix being described.Expressions in { } represent conditions that must be fulfilled in order to correctlyenter input. Recommended values for input are specified in ( ).
“ye will now go throughan example will be given.
the ACAB input one block at a time. For each card,
.“
42
-. -.—-... .....-.,..........><..<-l.+% - .-.
Block #kThe ACAB input file begins with a title card that gives a general description of
the calculation being performed. This card may contain character information andbe up to 80 characters in length (20 A4 format).
Example:
Activation of alumina first wall coating on NIF - single, 20 W yield
The 17$$ card is a “catch-all” that gives much of the general informationaboutwhat type ofcalculationis beingperformed.
17$$
f1
,2
3
4
5
6
7
All integer parameters [21]
ParameterITMAXIZMAX
MPCTAB
IR
JTo
NTABLE
MSTAR
Descri@ion
Number of nuclides in the decay data library (1875).Number of nonzero elements in the Transition Matrix(-lTMAX x average number of nuclear processes-30000,when fission products am not considered. Whenfission products are considered, IZMAX should be -61000).output option
O No effect1 Print radioactive concentration guides and must be
specified to perform calculation of biological hazardpotentials (see JTO).
output optionO No effect1 Print all elements of the Transition Matrix.
Output option (see Table IV):O Print all available tables for all isotopes, elements,
and most important isotopes for post-irradiationperiods. BHPs are provided only if MPCTAB = 1. IfNTABLE = 1, only tables for the most importantisotopes are printed.
1 Only selected output tables are printed. Tables areselected using the 8$$ card.
output OptiomO No effect1 Only tables for most important isotopes. Cutoff points
are selected using MSTAR and CUTOFF (7 card).Timestep used to select the most important isotopes. Thistimestep is chosen from the post-irradiation periods. Onlyisotopes with values greater than the thresholds given inCUTOFF are printed.Note If NTABLE = O,MSTAR has no effect
43
—.. .....
8 INPT
9 NPD
10 NOGG11 NGRP12 IGRP
13 IGE
14 IZM15 IM
16 JM
17 IFLU
18 IPRT
19 ILIB
20 IRAD
Input option1 Read initial concentrations as eiements.2 Read initial concentrations as isotopes.
Input option (see ISOZO on 5$$ card in block 5):O No effect1 Read continuous feed data for elements.2 Read continuous feed data for isotopes.
Number of energy groups for gammas emitted by decay.Number of energy groups for neutrons.Number of energy groups for gammas used in previoustransport calculations. IGRP will be nonzero only when fluxfiles obtained from coupled neutron-gamma transportcalculations are provided.Type of geometry:
One-dimensional:1 pIanar2 cylindrical3 spherical
Two-dimensional:1 x-y2 r-z3 r-fl
Three dimensional4 It is recommended for flux spatial distributions
from Monte Carlo neutron transport codesNumber of material zones.Number of spatial intervals in l-D,in 3-D, or number of 1’1dimension spatial intervals in 2-D calculations.Number of 2~ dimension spatial intervals in 2-D calculations.Not used for 1-D or Monte Carlo calculations.Input option
O No effect1 Plux in BCD structure with PIDO free format2 Flux in binary tape.
output OptiorxO No effect1 Print scalar neutron flux.
output optionO No effect.1 Print a mean energy photon production data per
disintegration for all isotopes in NOGG-groupstructure.
Output option:O No effect1 Print concentrations (number of atoms) during
.
44
.. .... ...... ... ... ..-. .. . . . ----
.. .. ... .._._,.. .. ....—- —.-—..- .
!
21irradiation times for all isotopes.
IPUN Option for generation of unit%O No effect1 Print photon release rates (photons/ems-s)
in a NOGGgroup structure. Spatialdependece is included. This option is usefulas a source term for subsequent photonphoton transport calculations.
T End of block #1.
Example
17$$ 1373 25000 0 0 1011 0 18 175 0 4110 1001OT
This card indicates that there are up to 1373 isotopes in the decay library and
WtO - no~ro elements in th@Tfinsition Matrix. The first timestep is used todetermine the list of most important isotopes. Initial concentrations are read aselements. The neutron .fiux is in 175 groups and gammas produced by activationare to be divided into 18 groups. The geometry is 3-D from a Monte Carlotransport problem. There is one material zone that has only a singIe interval. Theflux is. given in the PIDO f%eeformat’ and concentrations are requested for allisotopes during the irradiation period. The ‘T’ can be placed at the end of the lineas in the _ple or may be on a separate line. The additional spacing betweengroups ,ofinputs is not required but helps in reading of input fries.
.’
45
i...... -.-.- . .. .x. . . . . . . . . . . .
. . . , ,... ~.v . . ...<..-
.. ....... .....- ...-— —- ~. -.
Block #2The second input block contains detailed information about the current
calculation. The user can elect to receive zonal results by solving the transmutationequations by interval or by using a spatially-averaged flux for the entire zone. Thespatially-averaged flux @&for a zone K & defined by the following equation
where&I is the scalar neutron flux in energy group g and interval 1in zone ~AVlis the volume of interval 1in zone w andV. is the volume of zone K.
1- XRR,,
2* -“ YZT,’
3$!$ “MA
4$$ NUQO.
: 5$$ Isozo
6* EGRP
>.:
8$$ NTO
T
Boundaries for 1* dimension intervals in cm. For 3-D (IGE = 4)configurations, this card gives the volume of each zone in cmsand must end with an additional nonzero value. ~ + 1].BoWdaries for 2~ dimension intervals in cm. This card isomitted when 1-D or 3-D geometry is choiwn by the IGEparameter. ~ +1] ~M > O}.Zone number. identification of each spatial interval, goingfrom left to right and bottom to top. ~ or @l x ~.
Number of initial elements or isotopes per zone. Negativevalues am used when zone averaged fluxes are used. A zero(0) must be included to omit a zone. ~MJ.Number of elements or isotopes per zone for continuous feed.[IZMJ {INDF > 0}.Energy boundaries for gammas produced by activation.These boundaries are given in order of decreasing energyin MeV. [NOGG + 1] {NOGG > O}.7* CUTOFF Threshold values for different output tables.Any isotopes whose value in the timestep MSTAR falls belowCUTOFF will be omitted from the corresponding output table.One threshold value must be given for each of the six types.The six types of output tables are described in Table 15. [6].Allows selection of desired output tables. The 18 valuescorrespond to the 18 tables (three of each type) described inTable 2. [18] ~0 = 1}.
O No effect1 Print output table.
End of block #2.
46
..............e=
_--. -.-— . . . . . . .
_—— ——— -- -
Example #1:
1“ l.3684E+5 1.03$$ 14$s 36+. 11.0 8.0 6.0 4.0 3.0 2.5 2.0 1.5 1.0 0.7 0.45 0.3
0.15 0.1 0.07 0.045 0.03 0.02 0.07.* 1.OE+O 1.OE-6 1.OE+O 1.OE-3 1.OE+O 1.OE+O8$S 000 001 001 000 000 000T
Thisexampleisfor a3-Dgeometrydescription. Only asinglezone isincludedwith a volume ofl.3684E+5 cc (a nonzero vaiue ends the le card). The zone isnumbered as zone #1 and three initial elements will be given. A total of 19energies are given creating an 18-group structure for gamma-rays produced byactivation. Only 2 of the 18 tables have been requested (table #4 is grams of themost important isotopes and table #7 is activity in Bq of the most importantisotopes). Cutoff values have been specified for each of the table types. Agaim the“T” signi$ing the end of this block has &n included at the end of the 8$$ card,but could be placed on a separate line.
Example #2
3$$ 111 2222 334s.$ 3 3 6
This example is for a case with three zones. There are three intervals in thefirst zone, four intervaIs in the second zone, and two intervals in the third zone.The transmutation equations will be solved by intervals for all three zones,because all values of NUCZO are positive. The number of nuclides or elements ineach zone are 3,3, and 6, respectively.
Example #3:
3$$ 111 2222 334$$ 3 0 -6
Agati three zones are included in this example. This time, the transmutationequations are solved by interval in the first zone, the second zone is ignored, andrgsults for the third zone are calculated using a zone-averaged flux. The first zonecontains three nuclides or elements and the third zone contairis six.
47
... .... .... .... .. ... .. ....<=...._+--. - ........-.-.>.........
TABLA15. Type of tables that are output by ACAB.
output TabIe Output Quantity Output ScopeTable # Type
1 all isotopes2 1 gram–atoms (moles) all elements3 most important isotopes4 all isotopes5 2 mass (grams) ; all elements6, most important isotopes7 all isotopes8 3 activity (Bq) ~ all elements9. most important isotopes10 all isotopes11 4 afterheat (W) all elements12 most important isotopes13 all isotopes14 5 BHP in air (m’) - all elements15 most important isotopes16 all isotopes17 6. BHF’ in water (m3) all eiements18 most important isotopes+
,.%
Note: The 18 ACAB output tables can be categorized into six types accordingto the quantity that is indicated ( grarns-atorns,mass~ctivity,afterhea~BHP inair,and BHP in water). Each of the six types may be generated for allisotopes~l elernents~d most important isotopes. Tables to be generated arespecified on the 8$$ card. If most important isotopes are to be outputted,cutoffs must be specified on the 7**card.
Block #3:Block #3 consists only of the 9- card which inputs the energy- and spatially-
dependent fluxes. Block #3 is needed only if IFLU = 1.
F FLUX
i.e. JM = O,
Muitigroup scalar fluxes of neutrons and ~ammas (nlcm~sk[(NGRP +-IGRP)JM] for JM >0.
x IMl for JM = O,or [(NG~P + IGR~ x IM ~
1st group - spatial intervals from 1 to I’M.2nd group - spatial intervals from 1 to IM....
...
. . ...
NGRP group - spatial intervals from 1 to IM.‘gammas H ‘NGRP + 1 group - spatial intervals from 1 to IM..........NGRP + IGRP - spatial intervals from 1 to IM.
T End of block #3.
Example
9*.
O.OOOOOE+OO O.OOOOOE+OO 0.0000OE+OO 0.0000OE+OO 0.0000OE+OO O.0000OE+OOO.OOOOOE+OO O.0000OE+OO 0.0000OE+OO O.0000OE+OO 2.24560E+12 1.28748E+099.36590E+09 1.09117E+11 5.71239E+1O 2.29345E+1O 2.24553E+1O 2.21273E+1O2.O7259E+1O 2.42329E+1O 1.932OSE+1O 2.33644E+1O 3.29684E+1O 3.10372E+1O2.67600E+I0 2.73849E+1O 2.78341E+1O 3.11134E+1O 2.99179E+1O 4.24145E+1O4.27637E+1O 5.38507E+1O 4.97128E+1O 5.6037OE+1O 6.80981E+1O 5.99109E+1O7.O2953E+1O 8.36346E+1O 9.O5295E+1O 1.14939E+11 1.06675E+11 1.57469E+111.41095E+11 1.46795E+11 1.70587E+11 1.77039E+11 1.96036E+11 2.06424E+112.20851E+11 2.64793E+11 2.26939E+11 3.27008E+11 3.53680E+11 2.67274E+111.86971E+11 1.85623E+11 1.61273E+11 1.04622E+11 2.06572E+11 1.62587E+111.40515E+11 2.66758E+11 3.28667E+11 5.34534E+1O 1.36869E+11 2.55764E+111.80476E+11 8.37936E+1O 2.71935E+1O 1.90595E+11 2.07160E+11 1.67033E+111.51164E+11 1.10752E+11 8.90825E+1O 1.05012E+11 3.98039E+1O 3.85728E+1o3.90367E+1O 3.37028E+1O 3.35326E+1O 5.O6135E+1O 6.28872E+1O 6.67807E+1O6.35506E+1O 4.52059E+1O 3.1928OE+1O 4.79158E+1O 3.39836E+1O 1.50696E+1O1.88315E+1O 3.65922E+1O 1.72076E+1O 5.67439E+1O 2.29198E+1O 4.53192E+1O8.10556E+1O 1.58072E+1O 1.52956E+1O 1.53275E+1O 1.60421E+1O I.56105E+1O1.49453E+1O 1.95372E+1O 1.23915E+1O 1.68609E+1O 1.69424E+1O 1.87165E+1O1.77789E+1O 1.13412E+I0 3.76854E+09 8.06483E+09 7.66558E+09 7.87956E+091.42777E+1O 9.44282E+09 8.04090E+09 4.57391E+09 8.45258E+09 1.32726E+1O4.45566E+09 1.27853E+1O 4.53097E+09 8.68020E+09 9.08462E+09 1.53207E+1O
49
i. .. . .. ..... ... . ... ......._..—-.=G-_<=zcsQTcsQT—-..
5.39231E+09 1.53635E+1O 1.13034E+1O 9.46579E+09 1.11856E+1O 5.90132E+091.59676E+1O 5.75868E+09 1.O385OE+1O 1.12432E+1O 1.70752E+1O 1.86777E+1O1.80729E+1O 1.41357E+1O 6.93439E+09 1.64552E+1O 1.38189E+1O 1.68749E+1o1.51662E+1O 2.3588OE+1O 2.36985E+1O 1.64662E+1O 2.58199E+1O 1.63296E+1O2.85504E+1O 4.O1943E+1O 3.27129E+1O 3.57419E+1O 4.94656E+1O 3.82529E+1o4.33785E+1O 6.86971E+1O 5.28651E+1O 5.69083E+1O 6.72074E+1O 5.57159E+1O8.78042E+1O 7.18OO4E+1O 3.507O6E+1O 4.O1719E+1O 4.58855E+1O 4.78985E+1o5.17701E+1O 5.87309E+1O 6.69443E+1O 3.50314E+1O 9.78391E+11 0.0000OE+OO0.0000OE+OO T
This example gives the 175-group energy-dependent neutron fluxes for asingle zone as calculated from a 14.1 MeV point source without inclusion ofgammas. Note that 14.1 MeV lies within group #n, and thus, the first10 energygroups havefluxes ofzero. SpeciaI.attention mustbepaid tothe factthatthe fluxesforthe highestenergy groupmustbegiven foreachzoneor intervalbeforethe 21XIgroup begins.
It is worth noting that in a general case, thee nergydependent fluxesshouIdbegiven consistently with the cross Sections activation library. Ifcross sections amgiven as afunction of.decreasing/increasing energy, the neutron spectrum mustbe given following the same structure, that is, as a function ofdecreasing/increasing energy.
50
.... . ....
Block #4Block #4 allows for a RESTART OPTION, and is currently implemented for
one material zone and one interval. It contains one card that is read in FORTRANfree format The restart option can be very useful for calculations under pulsedirradiation regimes characteristic of conceptual KFE reactors., and it works asfollows.
ACAB produces in all inventory calculation runs the UNlT37, which containsthe composition in g-atom for all isotopes in the last time step of the problem. ThisUNIT can be used as input of new initial material composition if you want tocontinue the calculation in a new
Card #k
g Parameter Desmh3tion
run.
1 Indicator for restart option.O No effect1 The initial material composition is read from UNIT 37,
instead of using BLOCK #5 (this is used as explainednext for a non-restart case).
Example
oA non-restart case is considered, and UNIT 37 is not read. Initial composition
must be given in Block #5.
51
Block #5.Block #5 is used to specify the initial material composition in a non-restart run.
This Block must be omitted for a non-restart run. The nuclide identifier is definedas:
NUCLID= 1OOOOXZ+1OXA+IS
wherez= atomic number,A = atomic mass of nuclide, andIs= state indicator (O= ground state, 1 = first isomeric state,
and 2 = second isomeric state)
The identifier for an element follows the pattern set by the nuclide identifie~
ELEMID = 10000 X Z
This block must be repeated if more than one material zone is to be considered(including the “T” that denotes the end of the block).
10$$ INUCL Identifiers of the initial elements or isotopes. [NUCZO].11* XCOMP Concentrations of the initial elements or isotopes given in
utits of atoms/barn-cm. ~UCZO].T End of block #5.
Example #1:
10$$ 80000 120000 13000011”” 6.09E-02 1.52E-02 3.05E-02 T
This example specifies that the elements oxygew magnesium, and aluminumare the initial constituents of the material being irradiated. They are present in 6.09x 1022,1.52 x 10~, and 3.05 x 1022atoms/cc, respectively (1024atoms/cc = 1 atomx barn-l x cm-l).
Example #2
10$$ 74186011** 6.00E-02 T
The second example is for the irradiation of lWV. It is present at an atomicdensity of 6.00x 1022atoms/cc.
52
Block #6Block #6 is used to specify materials that are subject to continuous feed. This
block must be repeated if more than one zone undergoes continuous feed. Thisblock is only required if INFD >0.
12$$ IDNUM Identification of the element or isotope with continuous feed.[I!30zo].
13* XFEED Feed rates in g-atoms (moles) per second. [ISOZO]{INDFD > O}.
T End of block #6.
Example
12$$ 26000013+. 1.00E+OO T
This efiinple indicates that na~ral iron is continuously fed at a rate of 1 g–,.. atoms~s. “
53
.
Block #7 and #&Blocks #7 and #8 are used to specify the irradiation and post-irradiation
tempcmd history. Here, the user selects the timesteps that will be used to reach thedesired irradiation time and the specific post-irradiation (coding) times at whichthe full output is generated. ACAB starts its internal clock at zero when thecalculation begins. Whenever an irradiation period ends, the clock is reset to zero.Whenever an irradiation period begins, however, the clock is not ~e~ Itcontinues from the previous cooling period (or zero if the calculation has justbegun).
Due to the nature of the computational solution (the matrix exponentialmethod), it is recommended that the irradiation times ramp up by factors of twoand the cooling times ramp up by factors of three (see example).
A “set?’ is defined as a grouping of a 14!$$ card and a 15- card. The 14$$ cardgivesl ACAB information about the number of irradiation and/or coolingtim&eps, and the 15-card provides the actual ti.mesteps.Up to 10 timesteps maybe specified within a set For more than 10 timesteps, multiple ~ts are required.Each set may consist entirely of irradiation entirely of coolin~ or of irradiationfollowed by cooling. Since the clock is initially set to zero, only the ending times ofthe timesteps must be provided.
Sets may be grouped into a “unit” that gets repeated a specified number oftimes and may be followed by additional sets. The use of units makes thedefinition of complex irradiation/cooling histories easier. A complete explanationof the use of units is given in Block #n, Card #3.
,.,.-.14$$ All integer
* Parameter1 MMN2 ,: MOUT
3 . NGO..
4
parameters [8]
Descri@ionNumber of irradiation timesteps on this card. [s 10].Number of total timesteps ( irradiation + cooling) on this card.[< lo].
Computation flow controlo No additional sets provided.1 Additional sets provided.
Timestep in last set considered start of new sekNo effect if there is no prior set and set are notgrouped into a unit ( that is, pulsing is not beingused).Usually, MSUB is selected to point to the lasttimestep in the previous set In the case of pulsin~MSUB for the first set of the unit must point to thelast timestep on the last set of the unit (see block #n,card #3).
54
. ................... ... .. .. .. ... ...—-. —---- ..—---
5 IUNIT
6 MFEED
7 IOUT
8 IPLOT
T
15* TIMES
T
Physical unit of the timesteps:1 Seconds2 Minutes3 Hours4 Days5 Years6 1(P years7 1(P years8 1(P years
Continuous feed optiomo No effect1 Continuous feed used in current set.
output optiono No effecL1 Print output tables by spatial interval.
Preparation of data for plotting (generation of unit 11):o No effect- unit 11 is not generated.1 Output tables by interval.2 Output tables by zone.
End of block #7.
Ending times of each timestep. Note that the clock is set tozero when the calculation begins and is reset to zero wheneveran irradiation period ends (shutdown). [MOUT1.End of block #8.
Blocks #7 and #8 must be repeated for all time sets of interes.
Example
14$$ 1010101000 T15++ 1.0000E+O 2.0000E+O 4.0000E+O 8.0000E+O 1.6000E+1
3.2000E+1 6.4000E+1 1.2800E+2 2.5600E+2 5.1200E+2 T14$$ 10101101000 T15*’ 1.0240E+3 2.0480E+3 4.0960E+3 8.1920E+3 1.6384E+4
3.2768E+4 6.5536E+4 1.3107E+5 2.6214E+5 5.2429E+5 T14$$ 10101101000 T15” 1.0486E+6 2.0972E+6 4.1943E+6 8.3886E+6 1.6777E+7
3.3554E+7 6.7109E+7 1.3422E+8 2.6844E+8 5.3687E+8 T14$$ 331101000 T15’* 7.0000E+8 8.2500E+8 9.4608E+8 T14$$ 010 1 3 1 0 0 0 T15** 1.0000E+O 3.0000E+O 1.0000E+l 3.0000E+l 1.0000E+2
3.0000E+2 1.0000E+3 3.0000E+3 1.0000E+4 3.0000E+4 T14$$ 010 1 10 1 0 0 0 T~5** 1.0000E+5 3.0000E+5 1.0000E+6 3.0000E+6 1.0000E+7
3.0000E+7 3.1536E+7 6.3072E+7 1.5768E+8 3.1536E+8 T14$$ 0 6 010 1 0 0 0 T15’* 6.3072E+8 l.5768E+9 3.1536E+9 6.3072E+9 1.5768E+1O
3.1536E+1O T
55
....- .,-. ...-.-------— ----------.—----—--—--’---- —---------”-
In this example, the irradiation lasts for a total of 9.4608 x 1(P seconds (30years). The irradiation timesteps ramp up by factors of 2 from 1 second to 30 years.The last irradiation time occurs on the 4* set The cooling times begin on the 5* setand increase in most cases by factors of 3. Occasionally, the ratio between twocooling times is less than 3, because a specific cooling time is desired. For example,the 6* set has successive cooling times of 3.0 x 107 seconds and 3.1536 x 107
seconds. The latter time was selected as it corresponds to 1 year of cooling.
In this example, the irradiation and cooling times were kept on separate cardsin order to make them easier to understand. This is not required. The first 7cooling times froni the 5* set could have been placed on the end of the 4* set Thisresults m the 4* set looking like this
14$$ 10101101000 T15*’ 7.0000E+8 8.2500E+8 9.4608E+8 1.0000E+O 3.OOOOE+O
1.0000E+l 3.0000E+l 1.0000E+2 3.0000E+2 1.0000E+3 T
Note that the cooling times are still given relative to the end of the irradia-tionperiod, because the cbck is reset to zero when the irradiation period ends. Also,attention must be paid to the fact that each 14$$ card and each 15* card must endwith a “T” as they constitute individual blocks of input data.
56
.. .. .. . . .-.’,-.,. . . .
Block #9Block #9 tells ACAB what truncation error is allowable and allows the user to
scale the total flux (so that ail of the fluxes don’t have to be multiplied by 75%, forexample).
16M All floating point parameters [2]
g Parameter Description1 ERR Truncation error (lo-~).2 XNORM Normalization factor (1.0). If XNORM is negative, a test
printout of the neutron-induced transmutation rates byinterval or zone will be given. The resulting output may bequite voluminous.
T End of block #9
Example
16** 1.OE-25 7.50E-01 T ,,
This example uses the standa~ truncation error, but tells ACAB to scale all ofthe fluxes by a factor of 0.75. ~is.might be done if the user desired to simulate 40yeak of op&ation at 75% of capaci~,’ for example.
57
Block #1o
The FORTRAN free format is used to read block #10. This block is used to controlthe computing of fission product inventory.
Card #1:
~ Parameter1 IGFP
Descri@ion
Option to caiculate the inventory of fission products if actinideswere initially present
O No effect All nuclear reactions, including fission, areconsidered in the calculation. But fission yield dataare assumed to be zero (UNIT 96 is not read).
1 Fission products are incIuded in inventorycalculations. (UNIT % must be given).
Type of effective fission yield cross section library (UNIT%).No effect if IGFP is equal to zero.
O Weighted fission yield cross sections for allfissionable nuclides included in the basic fissionyield data library (JEF-2.2) are read.
1 Effective fission yield cross sections for all fissionablenuclides included in the activation library (UNIT 4)are read.
Example #1:
11
,,This card tells ACAB to read UNIT % that includes fission yield cross sectionsfrom ail the fissionable nuclides in the activation library.
Exan@e #2
o ‘-1
The UNIT % is not mad, so ACAB does not deal with fission products. It doesmdmatter the value of the second parameter.
58
Block #n:The four cards are read by ACAB as FORTRAN free format These cards tell
ACAB about the lype of run (for pathway analysis or inventory calculations) andtype of output desired and allow the user to define the operational scenario(irradiation/cooling history) in terms of a “unit”.
Card #k
~ Parameter Descri@ion1 IWP Type of ACAB run. Options for UNIT 31 and UNIT 32
1 Reading and processing of the decay and cross sectionlibraries. Transition matrix information and somecontents from the decay library ( such as decay heat,natural isotopic abundances, etc) are written in UNIT31. This unit can be read from inputs files withIWP=3. ACAB can make a run for inventorycalculation if the second parameter of this card IMTX,is not equal to 1.
2 Reading UNIT 31, previously generated in runs withIWP=l. Decay and cross sections libraries are notrequired as inputs. ACAB can proceed for inventorycalculations if IMTX is not equal to 1.
3 Run for pathway analysis. Generates unit 22 whichgives the number of nuclides on the decay library, thenumber of non-zero terms on the transition matrix,parents and processes by which the different isotopesare produced. ACAB execution stops after unit 22 iswrit&n. This file is required for operation of theCHAINS code (see Section VIII).
2 IMTX Transition matrix option. Generation of UNIT 24:0 Run for inventory calculation. No generation of UNIT
241 Run for pathway analysis. Generates unit 24 which
contains the elements of the transition matrix. ACABexecution stops after unit 24 is written. This file isrequired for operation of the CHAINS code (seeSedon VIIl).
2 Run for pathway analysis and inventory. Unit 24 isgenerated, but ACAB execution continues for a fullinventory run.
3 IWDR Jsotopic Waste Disposal Ratingso No effect1 Generates total and isotope-dependent Waste
59
Disposal Ratings4 IDOSE Dose rate requesk:
o No effect1 Dose rates estimates are requested - an additional
input line must appear.5 IPHCUT Photon energy cutoff options:
o Only include photons with energies >100 keV1 Use full energy range for photons
..
60
. ....... .... .
Card #2
Card #2 only appears if IDOSE = 1. Card #2 is used to specify what type ofdose rate estimates are desired. Three of the calculated dose rates are contact doserates that would be experienced at the surface of a semi-infinite media thatcontained radionuclides in the calculated concentrations. The fourth dose rate iscalculated for a very thin layer of material that contains radionuclides in thecalculated concentrations.
ParameterII ~H1
2 BREM
3 TOT
4 RHOR
Card #3:
DescriptionPhoton dose rate in Sv/hour.
O No dose rate.1 Print dose rate.
Bremsstrahlung dose rate in Sv/hour.O No dose rate.1 Print dose rate.
Photon + Bremsstrahlung dose rate in Sv/hour.O No dose rate.1 Print dose rate.
Dose rate per unit thickness from a very thin layer (materialthickness <<photon mean free path in material) in units ofSv/hour-cm.
O No dose rate. ,,1 Print ,dose rate.
,,
When IDOSE = O,card #2 will not appear, and thus, card #3 will immediatelyfollow card #1. Complicated irradiation/cooling histories can often be simulatedby defining a “unit” of sets that gets repeated a spified number of times. Thisunit can be followed by additional sets. Figure 3 demonstrates the concept ofdefining a unit Card #3 must be specified even when the unit will not berepeated.
g Parameter1 NOPUL2 NTSEQ3 Nom4 NVFL
DescriptionNumber of times to repeat the unitNumber of sets within a unitTotal number of sets. { NOT’IT < 150}Flux scaling factors that allow the reference flux for each set tobe scaled.
o Flux scaling factors not used.1 Flux scaling factors are used and are given on the
FVAR variable on card #4.
61
.. .. .
Card #4
When NVFL = 1, the FVAR variable will be given to specify irradiation scalingfactors for each irradiation period.
# Parameter Description1 FVAR Flux scaling factor for each set in the unit and for additional
sets that follow the unit [NOlT?3]. FVAR is only requiredif the scaling factors are different from unity Forpure “cooling” sets FVAR may take any value.
Example #1:
100111111149 29 30 11. 1. 50. 1. 1. 50.1. 1. 200. 1. 1. 1.50. 1. 1. 1. 50. 1.1. 200. 50. 1, 1. 50.1. 1. 50. 1. 1. 200.
This example requests each of the four dose rates using the full range ofphoton energies. 29 sets are defined as a unit The unit is repeated 149 times (149repetitions + original loop = 150 total times through the unit) and followed by afinal set (30 total sets). The specified flux is to be multiplied by factors of 1,50, and200 for the various irradiation periods. The flux of the final set is to be multipliedby a factor of 200 (30 scaling factors are given as there are 30 sets). The listing ofsets for this example appears in Section VL
Example #2
14$$12121OOOT15” 1.0000%6 1.99999E-1 T14$$11OO21OOOT15” 2.OOOOOE-1 6.000E-1 1.8000E+0 5.4000E+0 1.6200E+1
4.8600E+1 1.4580E+2 4.3940E+2 1.3122E+3 3.6000E+3 T20011111117998 1 2 0
In this example, the sets have been shown to provide a full explanation. Thefirst set is defined as a UNL In this case, irradiation takes place over 1 us, foUowedby nearly 200 ms of cooling. The unit gets repeated 17998 times for a total of 17999irradiation/cooling cycles. A final set gives another 1 PS of irradiation and isfollowed by a sen:= of cooling times. !%ce eachsame flux, NVFL = Oand card #4 is not required.
62
of the. irradiations is to use the
..... . .. . ......... .----. - -. ---.—- —------- -- —---—--—------———-— ---—
\
Note that MSUB = 2 for the first set. This is necessary as each new irradiationwill follow the cooling timestep in the previous loop. Also note that the irradiationtime on the final set is given as 0.2 seconds. This is done, because the irradiationbegins when the cooling ends at 0.199999 seconds in the previous set. Theirradiation ending time of 0.2 seconds results in the final irradiation lasting for Ius.
Example #2 simulates the operation of a Inertial Fusion Energy (IFE) powerplant that is operating at 5 Hz for 1 hour.
63
/ .... .. . .. .. ........- --.....-
VI. Example problems.
Some examples of the exact text of the entire ACAB input fiIe are nowgiven. Foilowing the texc a description of the input is given for each example.
The first example demonstrateshow ACAB handle problems with differentzones, and a pulsing irradiation scenario. The modelling of this irradiationschedule by using time sets grouped into a unit and flux scaling factors is shown.
Example #1:
.-.
30 years in NIF - 385 MJ/year + final, 20 MJ shot - chader & shielding17$$ 1373 25000 0 0 1121 0 18 175 0 4220 lo OIOT1*+ 3.20484E+7 6.79673E+07 1.03$$ 1 24$$ 9 186.● 11.0 8.0 6.0 4.0 3.0 2.5 2.0 1.5 1.0 0.7 0.45 0.3
0.15 0.1 0.07 0.045 0.03 0.02 0.07** l.oE+o 1.oE-6 l.oE+o 1.oE-3 l.oE+o l.oE+o8$$ 000 100 100 001 000 000T9.+
.0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .(10000E+OO .0000OE+OO
.0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO
.0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .oOOOOE+OO .0000OE+OO
.0000OE+OO .0000OE+OO 3.75283E+09 1.06790E+09 2.41546E+08 1.64104E+O83.84590E+08 1.64365E+08 3.92236E+08 1.74657E+08 2.94620E+08 1.35003E+082.25813E+08 1.00259E+08 2.60161E+08 1.14627E+08 2.06422E+08 8.98104E+o71.97115E+08 7.97792E+07 1.74955E+08 7.02182E+07 1.80717E+08 7.42934E+071.56673E+08 6.05528E+07 1.85038E+08 6.75537E+07 1.65204E+08 6.31651E+071.38058E+08 5.96646E+07 1.52241E+08 6.72402E+07 1.69858E+08 9.00193E+071.62767E+08 9.35198E+07 1.601O8E+O8 8.82952E+07 2.08528E+08 1.05223E+081.92572E+08 1.04753E+08 2.63707E+08 1.30249E+08 2.421OOE+O8 1.15985E+082.84870E+08 1.28315E+08 3.34619E+08 1.40907E+08 3.03152E+08 1.29047E+083.66419E+08 1.39705E+08 4.11183E+08 1.56006E+08 4.53620E+08 2.06475E+085.78825E+08 2.89493E+08 5.55778E+08 2.84791E+08 7.95108E+O8 4.07725E+087.68073E+08 3.44926E+08 8.37434E+08 3.08563E+08 1.01416E+09 3.5851OE+O81.10435E+O9 3.91059E+O8 1.24540E+09 4.57359E+08 1.40274E+09 4.45708E+081.52573E+09 4.01926E+08 1.92129E+09 4.29407E+08 1.71520E+09 6.37398E+082.55618E+09 8.18168E+08 2.94288E+09 9.70203E+08 2.34344E+09 5.65298E+081.70966E+09 3.15460E+08 1.67864E+09 4.00307E+08 1.45149E+09 4.54799E+089.49233E+08 2.87247E+08 1.93126E+09 4.23765E+08 1.52241E+09 4.96752E+081.39942E+09 4.01508E+08 2.67141E+09 1.11701E+09 3.42597E+09 9.25271E+085.52122E+08 4.02344E+08 1.50246E+09 4.72824E+08 2.73346E+09 5.97168E+081.86478E+09 5.59029E+08 9.18873E+08 4.33221E+08 3.09689E+08 3.77684E+082.19940E+09 5.64776E+08 2.36228E+09 6.40532E+08 1.94345E+09 7.87865E+081.77836E+09 8.76160E+08 1.26092E+09 6.68223E+08 9.95437E+08 5.65821E+081.20773E+09 6.50459E+08 4.24479E+08 2.32284E+08 4.38994E+08 2.31605E+084.18052E+08 1.95399E+08 3.75394E+08 1.88816E+08 4.11737E+08 3.43829E+085.88021E+08 3.72669E+08 6.92728E+08 3.85469E+08 7.32506E+08 4.08143E+087.39929E+08 4.39491E+08 5.01375E+08 2.93046E+08 3.44480E+08 2.02034E+085.17884E+08 3.06891E+08 3.94119E+08 2.36830E+08 1.75620E+08 1.06999E+082.14068E+08 1.31920E+08 4.01321E+08 2.51041E+O8 1.91686E+08 1.17919E+086.51621E+08 4.19429E+08 2.72460E+08 2.99054E+08 4.88633E+08 3.42993E+089.10674E+O8 5.40221E+08 1.69747E+08 1.00259E+08 1.67420E+08 1.03499E+081.69858E+08 1.04753E+08 1.73293E+08 1.08149E+08 1.76506E+08 1.11963E+081.78168E+08 1.14157E+08 2.22489E+08 1.41586E+08 1.48030E+08 9.76995E+07
64
1.90689E+08 1.24502E+08 1.98666E+08 1.27688E+08 2.01769E+08 1.33018E+082.0852.8E+081.37249E+08 1.29194E+08 8.43768E+07 4.13731E+07 2.80873E+078.63251E+07 5.90376E+07 8.55163E+07 5.86719E+07 8.90176E+07 6.00303E+071.39166E+08 9.16390E+07 9.21532E+07 6.18589E+07 9.12003E+07 6.35830E+074.64256E+07 3.21572E+07 9.55770E+07 6.40532E+07 1.47809E+08 9.95803E+074.76999E+07 3.30506E+07 1.53570E+08 1.02558E+08 4.9661OE+O7 3.47382E+071.02912E+08 6.99047E+07 1.02546E+08 7.13676E+07 1.60329E+08 1.09611E+085.31402E+07 3.71676E+07 1.62656E+08 1.13060E+08 1.1OO81E+O8 7.75849E+071.14125E+08 7.92045E+07 1.18446E+08 8.07196E+07 6.01761E+07 4.07934E+071.81049E+O8 1.25546E+08 6.15500E+07 4.27892E+07 1.25094E+08 8.69891E+071.26092E+08 8.88699E+07 1.92905E+08 1.35996E+08 2.04317E+08 1.41168E+082.06755E+08 1.46967E+08 1.44263E+08 1.01513E+08 7.12562E+07 5.04328E+071.47144E+08 1.05641E+08 1.54567E+08 1.08514E+08 1.60662E+08 1.10343E+o81.60662E+08 1.13687E+08 2.50078E+08 1.77217E+08 2.64039E+08 1.85995E+081.78611E+08 1.27897E+08 2.81546E+08 2.02452E+08 1.90578E+08 1.40854E+083.05479E+08 2.19954E+08 4.41764E+08 3.23453E+08 3.4171OE+O8 2.52242E+083.64203E+08 2.73715E+08 5.28853E+08 3.94142E+08 4.34783E+08 3.22617E+084.47636E+08 3.42157E+08 6.86745E+08 5.24024E+08 5.92453E+08 4.60703E+086.21372E+08 4.84213E+08 7.30511E+08 5.77315E+08 5.44144E+08 4.39177E+089.35383E+08 7.701O2E+O8 7.73835E+08 6.50459E+08 3.65865E+08 3.20736E+084.38883E+08 3.88133E+08 4.83093E+08 4.30714E+08 5.25640E+08 4.83795E+085.70847E+08 5.48057E+08 6.32896E+08 6.46279E+08 6.90512E+08 7.43456E+083.68414E+08 4.27945E+08 9.56102E+O9 1.69328E+1O .0000OE+OO .oOOOOE+OO.0000OE+OO .0000OE+OO
To IREST10$$ 120000 130000 140000 220000 240000
250000 260000 290000 3000001~,. 2.944E_03 5.632E-02 2.316E-04 5.093E_05 4.69~E_oS
2.072E-04 1.165E-04 2.559E-05 6.218E-05 T10$$ 10000 50000 60000 80000 110000
120000 130000 140000 190000 200000210000 220000 240000 250000 260000280000 290000 300000
1~** 1.304E-02 8.070E-04 1.094E-04 4.345E-02 9.146E_04
2.337!5-044.059E-03 1.578E-02 4.369E-04 1.443E-032.923E-05 2.961E-05 2.00IE-06 8.839E-06 3.344E-042.239E-05 1.092E-06 2.653E-05 T
‘Define unit as 29 shots‘Unit time length is 72 days = 20x1.25‘Repeat unit 150 times to get 30 years‘Shot #1 - 100 kJ + 1.25 days cooling14$$24141000 T15*. 5.000oE-l l_ooooE+o 6.4800E+4‘Shot #2 - 100 kJ + 1.25 days cooling14$$24141000 T15** lo.8ooo5E+4 lo-8ooloE+4 6.4800E+4
‘shot #3 - 5 MJ + 5.0 days cooling14$$25141000 T15** lo.8ooo5E+4 lo.8ooloE+4 8.6400E+4
‘Shot #4 - 100 kJ + 1.25 days cooling14$$24151OGO T15** 43.2ooo5E+4 43.2ooloE+4 6.4800E+4
‘shot #5 - 100 kJ + 1.25 days cooling14$$ 2 4 1 4 1 0 0 0 T15*. lo.8ooo5E+4 lo.8ooloE+4 6.4800E+4
‘Shot #6 - 5 MJ t 5.0 days cooling14$$ 2 5 14 1 0 0 0 T15.* lo.8ooo5E+4 lo.8ooloE+4 8.6400E+4
‘Shot#7 - 100 kJ + 1.25 days cooling
65
+ 7x5.O + 2x6.O
1.0800E+5 T
1.0800E+5 T
2.5920E+5 4.3200E+5 T
1.0800E+5 T
1.0800E+5 T
2.5920E+5 4.3200E+5 T
1-—.——.-... . . . . . . ........ ..... ...
14$$ 24151000 T15” 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #8 - 100 kJ + 1.25 days cooling14$S24141000 T15” 10.8OOO5E4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #9 - 20 MJ + 6.0 days cooling14ss 2 5 1 4 1 00 0 T15** 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 5.1840E+5 T‘Shot #10 - 100 kJ + 1.25 days cooling14SS24151000 T15” 51.84005E+4 51.8401OE+4 6.4800E+4 1.0800E+5 T‘Shot #11 - 100 kJ + 1.25 days cooling14SS24141000 T15’* 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #12 - 100 kJ + 1.25 days cooling14S$24141000 T15** 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #13 - 5 MJ + 5.0 days cooling14SS25141000 T15** 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 4.3200E+5 T‘Shot #14 - 100 kJ + 1.25 days cooling14S$24151000 T15** 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #15 - 100 kJ + 1.25 days cooling14ss 2 4 1 4 1 0 0 0 T15” 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T
; ‘shot #16 - 100 kJ + 1.25 days cooling14S$24141000 T15*’ 10.8OOO5E+4 10.8OO1OE+4 6.4.800E+41.0800E+5 T‘shot #17 - 5 MJ + 5.0 days cooling14$S2 5 1 4 1 00 0 T15’* 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 4.3200E+5 T‘shot #18 - 100 kJ + 1.25 days cooling14SS2 4 1 5 1 0 00 T15” 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T
.... ‘shot #19 - 100 kJ + 1.25 days cooling14SS2 4 1 4 1 0 0 0 T15+’ 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #2o - 20 MJ + 6.0 days cooling14SS2 5 1 4 1 00 0 T15” 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 5.1840E+5 T‘Shot #21 - 5 MS + 5.0 days cooling14SS”G?5151OOO T15*’.-S84005E+4+451.8401OE+4 8.6400E+4 2.5920E+5 4.3200E+5 T‘Shot’#22 - 100 kJ + 1.25 days cooling14!$$<24151000 T15** 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #23 - 100 kJ + 1.25 days cooling14$S24141000 T15” 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #24 - 5 MJ + 5.0 days cooling14SS25141000 T15” 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 4.3200E+5 T‘Shot #25 - 100 kJ + 1.25 days cooling14S.$24151000 T15** 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #26 - 100 kJ + 1.25 days cooling14$$2 4 1 4 1 0 00 T15+* lo.8ooo5E+4 lo.8ooloE+4 6.4800E+4 1.0800E+5 T‘Shot #27 - 5 MJ + 5.0 days cooling
64
?
14$$ 25141000 T15** 10.8OOO5E+4 10.8OO1OE+4 8.6400E+4 2.5920E+5 4.3200E+5 T‘Shot #28 - 100 kJ + 1.25 days cooling14$$ 2 4 1 5 1 0 0 0 T15” 43.20005E+4 43.2OO1OE+4 6.4800E+4 1.0800E+5 T‘Shot #29 - 100 kJ + 1.25 days cooling14$$ 24141000 T15** 10.8OOO5E+4 10.8OO1OE+4 6.4800E+4 1.0800E+5 T‘Additional 20 MJ shot - outside Of unit‘Get results at 12 h, 1 d, 2 d, 3 d, 5 d, 6 d, and 7 d14$$ 2 9 04 10 1 0 T15** 10.8OOO5E+4 10.8OO1OE+4 4.3200E+4 8.6400E+4 1.7280E+5
2.5920E+5 4.3200E+5 5.1840E+5 6.0480E+5 T16,* 1.OE-25 1.0 T00 IGFP IWFYD10111 IWP IMTX IWDR IDOSE IPHCUT1111 PH BREM TOT RHOR149 29 30 1 NOPUL NTSEQ NOTTS NVFL1. 1. 50. 1. 1. 50.1. 1. 200. 1. 1. 1.50. 1. 1. 1. 50. 1.1. 200. 50. 1. 1. 50.1. 1. 50. 1. 1. 200.
This example problem was used foracalculation of the neutron activationfor the National Ignition Facility (NIF)A1-5083 target chamber and inner portionoftheconcrete (withA1-5083 rebarandboron) shield.Theinput simulates30yearsofoperationof this facility.
Theneutron activation is to recalculated fortwozones. The zonalvolumesare givenon thel- card since Monte Carlo was used for the neutron transport(IGE = 4). The 3$$ card specifies that the first zone contains material #1 and”thesecond contains materiai #2. Material #lconsists of9eIemen&, and material #2iscomposed of 18 elements. The 8$$ card is used to request the various outputtables grams for all isotopes, activity for all isotopes, and afterheat for the mostimportant isotopes. The P gives cutoff limits for each of the types of outputtables. This card specifies that isotopes will only be included in mass tables if theyare present in more than 1 P~ in activity tables if they have an activity of morethan 1 Bq, and in afterheat tables if their decay heat is greater than 1 mW. Dummyvalues of 1.0 are specified for the remaining tables (that are not requested asoutput). The second timestep is used to impose the cutoffs.
The 175-group neutron fluxes are specified using the - card in descendingenergy order alternating between the first and second zone (highest energy forzone #1, highest energy for zone #z .... lowest energy for zone #1, and lowestenergy for zone #2).
A non-restart case is addressed (IREST=O), then initial composition is readfrom BLOCK #5 (cards 10$$ and ll-).The first occurrence of the 10$$ and 11-cards gives the composition for AI-5083. The second gives the composition forconcrete with A1-5083 rebar and boron.
67
....... .. ...... . .---. -..-=...-..—.-
i
Comments are given throughout the input file by placing a single quote (I)in the first column of an input line.
A total of 30 sets are given with the first 29 sets being defined as a unitwhich gets repeated a total of 150 times. Flux scaling-factors are used to change tototal flux level for each irradiation within the unit and for the final irradiation. Theuse of the flux scaling factors makes it possible to model 100 kJ, 5 MJ, and 20 MJfusion yields on the Ml?.
The generation of fission products is not addressed in calculation. (IGFP=O).
ACAB writes the complete output for one zone before starting another zone.Output tables appear in the order given in Table 15. Tables 16 through 21 areexcerpts of the ACAB output for the above example problem. Each output tableappears with the isotopes in rows and the various cooling times in columns. Hmore than 10 cooling times were requested, the first ten would have been given inone table and the remaining times would follow in additional table(s).
.,
68
-..
Table16. Example ACAB output. Isotopic masses are given for the Ml? A1-5083 target chamber as a functionof cooling time after 30 years of operation at 385 MJ/year plI.w a final, 20 MJ experiment. Isotopes with massesc 1 pg at shut-down were omitted from the output.
30 years in NIF - 385 MJ/year + final, 20 MJ shot - chamber & shieldingCONCENTRATIONS AFTER IRRADIATION (SUMMARY FOR MOST IMPORTANT ISOTOPES) BY ZONEVOLUNE OF ZONE : 3.20484E+07 CCM
NUCLIDE CONCENTRATIONS, GUAMSZONE 1
HE 3HE 4NE 20NE 21NE 22NA 23NA 24MG 24ZN 64ZN 66ZN 67ZN 68ZN 70TOTAL
SHUTDOWN 4.320E+04S 8.640E+04S 1.728E+05S 2.592E+05S 4.320E+05S 5.184E+05s 6.048E+05s2.37538E-06 2.37555E-06 2.37572E-06 2..376O5E-O62.37639E-06 2.37707E-06 2.37740E-06 2.37774E-061.28570E-03 1.28570E-03 1.28570E-03 1.28570E-03 1.28570E-03 1.28570E-03 1.28570E-03 1.28570E-039.56195E-05 9.56195E-05 9.56195E-05 9.56195E-05 9.56195E-05 9.56195E-05 9.56195E-05 9.56195E-051.90922E-04 1.90922E-04 1.90922E-04 1.90922E-04 1.90922E-04 1.90922E-04 1.90922E-04 1.90922E-042.67853E-05 2.67853E-05 2.67853E-05 2.67853E-05 2.67853E-05 2.67853E-05 2.67853E-05 2.67853E-os9.46986E-04 9.47025E-04 9.47025E-04 9.47025E-04 9.47025E-04 9.47025E-04 9.47025E-04 9.47025E-041.22221E-05 7.07716E-06 4.06184E-06 1.33798E-06 4.40734E-07 4.78223E-08 1.57528E-08 5.18901E-092.97014E+06 2.97014E+06 2.97014E+062.970111iI+062.97014E+06 2.97014E+06 2.97014E+06 2.97014E+061.02925E+05 1.02925E+05 1.02925E+05 1.02925E+05 1.02925E+05 1.02925E+05 1.02925E+05 1.02925E+056.09333E+04 6.09333E+04 6.09333E+04 6.09333E+04 6.09333E+04 6.09333E+04 6.09333E+04 6.09333E+049.09003E+03 9.09003E+03 9.09003E+03 9.09003E+03 9.09003E+03 9.09003E+03 9.09003E+03 9.09003E+034.22582E+04 4.22582E+04 4.22582E+04 4.22582E+04 4.22582E+04 4.22582E+04 4.22582E+04 4.22582E+041.43614E+03 1.43614E+03 1.43614E+03 1.43614E+03 1.43614E+03 1.43614E+03 1.43614E+03 1.43614E+038.65979E+07 8.65979E+07 8.65979E+07 8.65979E+07 8.65979E+07 8.65979E+07 8.65979E+07 8.65979E+07
69
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Table 18. Example ACAB output. Decay heat is given in Watts (W for the inner portion of the NIF concreteshielding as a function of cooling time after 30 years of operation at 385 MJ/year plus a final, 20 MJexperiment. Isotopes with a decay heat of <10’ W at shutdown were omitted from the output.
30 years’in NIFCONCENTRATIONSVOLUME OF ZONE
- 385 kf~lyear + final, 20 MJ shot - chamber & shieldingAFTER IRWDIATION (SUMMARY FOR MOST IMPORTANT ISOTOPES) BY ZONE
: 6.79673E+07 CCM
NUCLIDE THERMAL POWER, WATTSZONE 2
SHUTDOWN 4.320E+04S 8.640E+04S 1.728E+05s 2.592E+05S 4,320E+05S 5.184E+05S 6.048E+05SLI 8 3.06535E+02 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOBE 8 3.94222E+01 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO ,0000OE+OO .0000OE+OO .0000OE+OOBE 11 1.27081E+O0 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOB 12 8.74836E+02 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOB 13 1.46806E-01 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOC 15 1.45781E+01 ,0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OON 16 5.30969E+03 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OON 17 5.94580E-01 .0000OE+OO ,0000OE+OO .0000OE+OO .0000OE+OO ,0000OE+OO .0000OE+OO .0000OE+OOCO 63 5.56669E-01 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOCO 64 7.24420E-02 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOCU 62 6.83985E-02
.0000OE+OO.0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO
CU 66 1.06901E+oo 1.87211E-06 1.60762E-06 1.18547E-06 8.74170E-07 4.75344E-07 3.50521E-07 2.58476E-07CU 68 1.38220E+01 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOCU 68M 7,11591E-02 .0000OE+OO ,0000OE+OO .0000OE+OO .0000OE+OO ,0000OE+OO ,0000OE+OO .0000OE+OOcu 70 3.01830E-01 .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OOCU 70M 4.41572E-03
.0000OE+OO.0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO .0000OE+OO
TOTAL 1.58083E+04 1.26524E+oo 6.34546E-ol 2.68240E-ol 1.42457E-01 7.47877E-02 6.50719E-02 5,96567E-02
71
Table 19. Example ACAJ3 outp~t. Contact y-ray dose rate from a semi-infinite medium that contains the
calculated concentra-tions of each radionuclide is given in Sv~our for the NIF A1-5083 target chamber as afunction of cooling time after 30 years of operationat385MJ/year phs a final, 20 MJ experiment. Isotopesthat contribute less than 1 @v~oUr at shutdown were omitted from the output.
30 years in NIF - 385 MJlyear + final, 20 MJ shot - chamber & shieldingCONCENTRATIONS AFTER IRRADIATION BY ZONEVOLUME OF ZONE
*-ISOTOPE SHUTDOWNNE 23 6.776E-03
: 3.20484E+07 CCM
SURFACE DOSE RATES DUE TODECAY EMITTED PHOTONS IN SV/H
4.32E+04S 8.64E+04S 1.73E+05S 2.59E+05S 4.32E+05s 5.18E+05s 6.05E+05S.000E+OO .000E+OO .OOOE+OO .000E+OO .000E+OO .000E+OO .000E+OO
NA 24 7.151E-02 4.141E-02 2.376E-02 7.828E-03 2.579E-03 2.798E-04 9.217E-05 3.036E-05NA 24M 1.117E+02 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OONA 25 1.803E-02 .000E+OO .000E+OO .000E+OO .OtiOE+OO .000E+OO .000E+OO .000E+OONA 26 1.856E+O0 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOMG 27 8.927E-01
.000E+OO.000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO
AL 28 4.077E+01 3.361E-08 2.258E-08 1.o19E-08 4.599E-09 9.369E-10 4.228E-10 1.908E-10AL 29 6.195E-04 .000E+OO .000E+OO ,000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 66 1.772E-03 1.021E-OS 8.765E-09 6.464E-09 4.766E-09 2.592E-09 1.911E-09 1.409E-09CU 68 1.149E-01 ,000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 68t41.071E-03 .000E+OO .000E+OO ,000E+OO .000E+OO .000E+OO .000E+OO ,000E+OOCU 70 8.660E-04 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 70M 5.993E-05 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOZN 63 3.717E-06 7.61~E-12 1.559E-17 6.535E-29 2.740E-40 .000E+OO .000E+OO .000E+OOTOTAL 1.557E+02 4.285E-02 2.463E-02 8.411E-03 2.978E-03 4.690E-04 2.229E-04 1.212E-04
72
{
Table 20. Example ACAB output. Contact Bremsstrahlung dose rate from a semi-infinite medium thatcontains the calculated concentrations of eacl~ radionuclide is given in Sv/hour for the inner portion of theNIF concrete shielding as a function of cooling time after 30 years of operation at 385 MJ/year plus a final, 20MJ experiment. Isotopes that contribute less than 1 @v/hour at shutdown were omitted from the output.
30 years in NIF - 385 MJ/year + final, 20 MJ shot - chamber & shieldingCONCENTRATIONS AFTER IRRADIATION BY ZONEVOLUME OF ZONE : 6.79673E+07 CCM
BREMSSTRAHLUNG CONTACT DOSE RATE IN SV/H
ISOTOPE SHUTDOWN 4.32E+04S 8.64E+04S 1.73E+05S 2.59E+05S 4.32E+05S 5.18E+05S 6.05E+05sLI 8 2.937E-01 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOBE 11 6.144E-04 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOB 12 8.167E-01 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOB 13 1.366E-04 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOC 15 2.183E-03 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OON 16 5.995E-01 .000E+OO .000E+OO .000E+OO .000E+OO ,000E+OO .000E+OO .000E+OON 17 9.708E-05 .000E+OO .000E+OO .000E+OO .000E’+00 .000E+OO .00’0E+OON 18 6.117E-05
.000E+OO.000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO
O 19 4.079E-G5 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO ,000E+OOMN 58 1.291E-04 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOMN 58M 5.288E-06 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOco 62M 3.186E-05 8.347E-21 2.187E-36 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCO 63 7.755E-05 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCO 64 2.854E-05 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 62 4.242E-06 ,000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 66 8.330E-05 1.459E-lo 1.253E-lo 9.238E-11 6.812E-11 3.704E-11 2.731E-11 2.014E-11CU 68 1.273E-03 .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OOCU 70 8.416E-05
.000E+OO.000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO .000E+OO
TOTAL 1.805E+O0 1.141E-05 3.705E-06 1.082E-06 3.483E-07 4.643E-08 2.080E-08 1.094E-08
73
.
Table 21. Example ACAB output. calculated way spectrum isgiveninphotons/ems/second in each of the 18groups specified on the 6“* card. Tfie spectrum was calculated for the NIF A1-5083 target chamber as afunction of cooling time after 30 years of operation at 385 MJ/year plus a final, 20 MJ experiment, The
, spectrum can be used for subsequent photon transport to obtain a more accurate estimate of the targetchamber dose rate.
30 years in NIF - 385 MJ/year + final, 20 MJ shot - chatier &ACTIVATION GAMMA RAY SPECTRUM AS A FUNCTION OF TIME BY ZONEVOLUME OF ZONE % 3.20484E+07CCM
shielding
GROUP PHOTON RELEASE RATES, PHOTONS/CCM/SECZONE 1
EMEAN(MEV)
9.50E+O07.00E+OO5.00E+OO3.50E+O02.75E+O02.25E+O01.75E+O01.25E+O08.50E-015.75E-013.75E-012.25E-011.25E-018,50E-02‘5.75E-023.75E-022.50E-021.00E-02TOTALMEV/SEC
SHUTDOWN7.25E-179.1OE-103.29E+046.97E+044.68E+052.38E+051.82E+085.06E+067.09E+062.40E+092.94E+051.05E+055.05E+048.81E+038,30E+021.14E-011.04E+021.80E+042.60E+091.71E+09
TIME AFTER SHUTIXN4N4.32E+04S 8.64E+04S 1.73E+05S 2.59E+05S 4.32E+05S 5.18E+05S 6.05E+05s.00E+OO .00E+OO .00E+OO .OOE+OO .00E+OO .00E+OO .00E+OO.00E+OO .00E+OO .00E+OO .00E+OO .00E+OO .00E+OO .00E+OO
4.53E-01 2.60E-01 8.56E-02 2.82E-02 3.06E-03 1.OIE-03 3.32E-044.42E+OI 2.36E+01 7.”14E+O0 2.55E+O0 2.77E-01 9,11E-02 3.00E-027.13E+04 4.09E+04 1.35E+04 4.44E+03 4.82E+02 1.59E+02 5.23E+012.76E+02 1.09E+01 2.68E-02 9.20E-03 8.39E-03 8.03E-03 7.68E-035.76E+02 2.30E+01 9.47E-02 3.32E-02 1.58E-02 1.32E-02 1.18E-028.31E+04 4.90E+04 1.76E+04 6.83E+03 1.45E+03 8.11E+02 4.95E+025.19E+03 2.71E+03 1.81E+03 1.25E+03 6.04E+02 4.25E+02 3.02E+023.98E+O0 3.56E+O0 3.15E+O0 2.81E+O0 2.23E+O0 2.00E+OO 1.78E+O01.37E-01 1.12E-01 8.25E-02 6.55E-02 4.68E-02 4,08E-t)2 3.59E-021.85E+02 1.55E+02 1.09E+02 7.68E+01 3.90E+01 2.81E+01 2.04E+OI.1.97E-11 1.96E-11 1.93E-11 1.90E-11 1.84E-11 1.81E-11 1.79E-119.76E-02 8.54E-02 6.52E-02 4.99E-02 2.91)3-02 2.22E-02 1.70E-025.37E+O0 3.47E-02 1.45E-06 6.15E-11 7.67E-13 7.67E-13 7.67E-137.64E-02 5.13E-02 2.32E-02 1.05E-02 2.19E-03 1.OIE-03 4.81E-048.37E-13 3.37E-13 5.47E-14 8.89E-15 2.34E-16 3.80E-17 6.17E-182.20E-05 1.54E-06 7.39E-08 6.70E-08 6.64E-08 6.61E-08 6.58E-081.61E+05 9.28E+04 3.30E+04 1.26E+04 2.58E+03 1.42E+03 8.72E+023;06E+05 1.76E+05 6.07E+04 2.18E+04 3.67E+03 1.82E+03 1.03E+03
74
The second example shows an input file dealing with calculation of fissionproducts.
Example #2
Natural Uranium irradiated during 512 seconds17$$ 1875 80000 0 0 112102410 4110 1001OT1** 3.62298E+05 1.03$$ 14$$ 16** 20.0 14.0 12.0 10.0 8.0 6.5 5.0 4.0 3.0 2.5 2.0 1.66 1.441.22 1.0 0.8 0.6 0.4 0.3 0.2 0.1 0.05 0.02 0.01 0.007** 1.00E+OO 1.00E-06 1.00E+OO 1.00E-03 1.00E+OO 1.00E+OO8$$000 000 001 000 000 000T9+*9.67725E+’14T
o IREST10$$ 92000011” 2.306E-07 T14$$. 10 10 0 0 1 0 0 0 T15** 1.000E+OO 2.000E+OO 4.000E+OO 8.000E+OO 1.600E+01
3.200E+01 6.400E+01 1.280E+02 2.560E+02 5.120E+02 T
16- 1.OE-25 1.OE+OOT11 IGFP IWFYD32111 IWP IMTx IWD IDOSE
IPHCUT001001100 NOPUL NTSEQ NOTTS NVFL
Thisinputisused foracalculation oftheinventory coming from irradiationofnaturalUranium during512seconds.
Initial composition is read” from Cards 1~ and 11* ( non-restart caw,IllEST=O). Fission products are included in the”invent&y calculation (IGFP=l),and thefissionyields cross sections from all the fissionable nuclides included inthe activation library are considered (IWFYD=l).
Inexample#3 wesimulate thesamesituation thattheone simulated using
inputs examples #4 and #5 successively. With these three examples we illtitratethe use of the restart option ( parameter IIU?ST)as well as the new capabilities forsimulating a pulsed irradiation/cooling history.
Example #3
ACTIVATION OF SILVER. PULSED IRRADIATION SCENARIO. IREST=O, NOPUL=817$$ 1875 30000 0 0 112102410 4110 1001OT1** 3.62298E+05 1.03$$ 1
75
* .. . . . . . . .-------—- --” ---——- .......
4$s 16** 20.0 14.0 12.0 10.0 8.0 6.5 5.0 4.0 3.0 2.5 2.0 1.66 1.441.22 1.0 0.8 0.6 0.4 0.3 0.2 0.1 0.05 0.02 0.01 0.007*4 1.00E+OO 1.00E-06 1.00E+OO 1.00E-03 1.00E+OO 1.00E+OO8$$000 000 001 000 0009**
000T
9.67725E+14To IREST10$$ 47000011** 2.306E-07 T14ss 2 4 O41OOOT15** 2.5E-01 5E-01 2.5E-01 5E-01 T16** 1.OE-25 1.OE+OO T00 IGFP IWFYD .’10111 IWP IMTX IWDR IDOSE IPHCUT001081100 NOPUL NTSEQ NOTTS NVFL
Thisinputis used foracalcuIation of the neutron activation forAgunderapulsed irradiation scenario. Theonly setoftheinputis defined as anunit Inthiscase, irradiation takes places over 0.5seconds, followed by 0.5seconds ofcooIing.The unitgets repeated 8timesfora total of9irradiation/cooling cycles. Itis seenthatnoadditional setstothosethe unitmustbegiven to end up the simulation ofa pulsed irradiation scenario, as it was needed in the former ACAB version.
The initial material composition is read in cards 10$$ and 11* (IREST=O).
In the examples #4 and #5, we simulate the same scenario than in example#3.
Example #4:
ACTIVATION OF SILVER. PULSED IRRADIATION SCENARIO. IREST=O, NOPUL=517$$ .1875 30000 0 0 112102410 4110 lo OIOT1** “ 3.62290E+05.1.o
3$$ 14$$.;.16**- 20. o 14.o 12.0 10.0 8.0 6.5 5.0 4.0 3.0 2.5 2.0 1.66 1.441.22 1.0 0.80.6 0.4 0.3 0.2 0.1 0.05 0.02 0.ol 0.oo7*. 1.00E+OO 1.00E-06 1.00E+OO 1.00E-03 1.00E+OO 1.00E+OO8$$ 000 000 001 000 000 000 T9**
9.67725E+14To IREST10$$ 47000011” 2.306E-07 T14$$ 2 4 O41OOOT15” 2.5E-01 5E-01 2.5E-01 5E-01 T16** ~.oE_25 l.oE+oo T
.. 00 IGFP IWFYD
76
?
~ 0111 IWP IMTX IWDR IDOSE IPHCUT001 051100 NOPUL NTSEQ NOTTS NVFL
The only difference between input #3 and #4 is the value assigned to theparameter NOPUL.
In this case the unit gets repeated 5 ( NOPUL=5) times for a total of 6irradiation/cooling cycles.
Example #5: *
ACTIVATION OF SILVER. PULSED IRRADIATION SCENARIO. IREST=l, NOPUL=217$s 1875 30000 0 0 112102410 4110 1001 OT1** 3.62298E+05 1..03$$ 14s$ 16** 20.0 14.0 12.0 10.0 8:.06.5 5.0 4.0 3.0 2.5 2’.0’1.661.441.2.21.0,0.8 0.6 0.4 0.,30.2 0.1 0.05 0.02 0.01 0.007*. 1.00E+OO 1.00E-06 1.,00E+OO1.00F-03 1.00E+OO 1.00E+OO8s$ 00.0” 000 001 000 000 OOOT.9.** . . ‘,., ..
.“9.67725E+14 “T1 IREsT. ‘“.
14$$ 2 4 O41OOOT15’” 2.5E-01 5E-01 2.5E-01 5E-01 T16’” 1.OE-25 1.OE+OO To 0. IGFP IWFYD10111 IWP IMTX IWDR IDOSE IPHCUTo 0, 1 .0
,.,.21100” NOPUL NTSEQ “NOTTSNVFL
Thisinputisused forarestartproblem. TheparameterIREST=l tellsACABto read initialmatenal compositions from UNIT37.Cards 10$$andll-,corresponding toanon-restart problem, are notgiven.
Theunit(defined thesame thaninexamples #3and#4) gets repeated 2timesforatotal ofthreeirradiation/cooling cycles.
Thisinput#5together withtheUNlT37 written byarunusing file#4makeACABoutputthe sameresultsthan thosecomputedwith input#3.
Inputs#4and#5 tell ACABtocalculate for9cycles(6+3). Thisnumberofcyclesisthesame whenrunnigwith input#3.
77
i . . . . .. ...... ... .. .. ....- ... ...... ...--—--— —.-.. .
VII. Pathways analysis. Chains Code
CHAINS Description
The purpose of the CHAINS code is to generate and output the possiblepathways for the formation of a particular nuclide. AII possible pathways thatrequire up to a specified number of steps are ranked according to theirestimated importance to the total production of the nuclide. The user gives animportance cutoff that is used to truncate the list of possible pathways.
CHAINS has been modified to include in the pathway analysis all thenuclear processes implemented in the present version of ACAB.
CHAINS can be executed in three different modes. In the first mode(IFLAG = O),the code calculates all transmutation sequences that results in theformation of a particular radionuclide (variable IFINAL) with a maximumnumber of steps (variable NMAX) in the chain. No initial nuclide is specifiedwhen operating in this mode. In addition to giving the actual chains, the codeoutputs the coefficients (transmutation rates or probability per nucleus per unittime)of neutron reaction or radioactive decay corresponding to each step of thechain. The CHAINS output is given in order of increasing number of steps ofeach chain., That is, all two-step chains are given before three-step chains arelisted.
In the second mode of operation, CHAINS calculates all pathwaysstarting from a specified parent nuclide (INITIAL) that result in a specifieddaughter nuclide (IFINAL) and take no”more than NMAX steps: CHAINS also.. ....estimates the relative importance of each pathway. This is accomplishedthrough the use of a “pseudo probability” for each pathway. The pseudoprobabilities are summed over all pathways that are possible in NMAX or less
steps. This sum is the total pseudo probability. Each pseudo probability maybedivided by the total pseudo probability to get an estimate of the relativeimportance of each pathway.
The relative importances may not be an actual ranking of the relativecontributions from each pathway, but they are useful for distinguishing thosepathways that may be important from those that maybe negligible.
‘.
As output for the second mode of operation, CHAINS writes thepathways in order of decreasing relative importance. The user specifies a cutoffvalue with the PCNT variable. Pathways that contribute less than PCNTpercent to the total pseudo probability are omitted. The coefficients associatedwith each step in a pathway are also given.
The following example illustrates the concept of pseudo probabilityrankings described above. Assuming that there are two possible pathways forthe production of nuclide F from nuclide 1, the pathways might be written as
I.. . ........... ......... ...
I aAl )A &JA >B aCB )C aK(1) )F
I am >D aED )E aFE(2) >Fwhere:
aia~i+~~i+j
j
and:
a,arethecoefficientsofthetransitionmatrixthatgivethereaction(GO)or
decay (k) probability per nucleus per unit time,c is the energy-averaged reaction cross section,$ is the energy-averaged neutron flux,L is the radioactive decay constant, and
The pseudo probabilities can be written as:
I?l==x=x=x=al aA aB aC
The total and relative pseudo probabilities can be written as:
Ptot = Pi + P2
l?R, = ‘YP tot
PRz = ‘titot
The relative importances would be written into the CHAINS output file inorder of decreasing importance. If either of the relative importances is less thanthe value of PCNT, it would be omitted from the output.
In the third mode of operation, CHAINS searches for all cyclic pathwaysor “loops” that include a user-specified final nuclide IFINAL. All pathways areincluded that are possible within NMAX steps. As in the first mode ofoperation, the pathways are listed in order of increasing number of steps andthe transmutation rates are given for each step within a pathway.
79
CHAINS SuIJUortFiles
ln addition to a standard input file,CHAINS requirestwo ACAB-
produced filesfor itsoperation.Unit 22 is a binary filethat contains the
identifiersof the nuclidesfound in the decay library and the elements of thetransition matrix. Each element of the transition matrix contains the identifiercorresponding to the neutron reaction or decay process occurring within thatelement. Unit 22 is generated by ruining ACAB with IWP = 1.
Unit 24 is a binary file that contains the transition matrix transformationrates. It also contains the diagonal elements which give the total depletion rates.Unit 24 is generated by running ACAB with IMTX = 1 or 2.
Unit 23 is a temporary binary file that is created during a CHAINS run.
This filecontainsallpossiblepathways which are laterorderingaccording to
theirrelativepseudo probabilities.This filemay become quitelargebut may be
deletedafterCHAINS execution.
CHAINS Inuut/OutuutA CHAINS input file consists of five cards. Some card may be omitted
for certain types of operation. The structure of the CHAINS input file is nowdescribed. -
2 INITIAL 16
~ Variable Format Descri~tion1 IFLAG 13 Indicates mode CHAINS operation
mode:1 Pathways to produce nuclide
IFINAL.2 Pathways to produce nuclide
IFINAL from nuclide INITIAL.3 Cyclic pathways to produce
nuclide IFINAL.Identifier for the first initial nuclide.The nuclide identifier is defined in thesame manner as NUCLID in ACAB(10000 x Z + 10 x A + IS). INITIAL isomitted if IFLAG # 2.
3 IFINAL 16 Identifier for the final nuclide. Theidentifier s defined in the samemanner as INITIAL.
4 NMAX 13 Maximum number of steps consideredfor possible pathways. {NMAXs 10}.
5 PCNT F6.2 Output option only pathways withrelative pseudo probabilities greaterthan or equal to PCNT will be printed
.. .PCNT is omitted if IFLAG # 2.(O<QCNTs 100}.
1
80
.. .......... ............ ....... ... . ... .. ...
.- .-. ..... . .... .. .. ........— -.. .. .
Some example input and output are now given. First, a sample input filefor the first mode of operation.
Example #1:
1 IFLAG110240 IFINAL Na-242 NMAX
In this example, all pathways that result in the production of “Na thatrequire two or less steps will be given. An portion of the output from thisproblem is given below:
NUMBER OF ENCOUNTERED CHAINS NCHAIN= 69************** ************** ************* ************** ***************
CHAINS WITH 2 LINKS************** ************** ************* ************** ***************
MG 27 (B-) AL 27...(n,a) NA 24 ~~.. . .
MG 27 (B-) AL 27 tiELTA=l.2214E-03
AL 27 (n,a) NA 24 XSEC=l .6121E-13************** ************** *****.******** ************** ****
***********
S1 27 (B+) AL 27 (n, a) NA 24
S1 27. (B+) AL 27 DELTA=1.6503E-01AL 27 (n, a) NA 24 XSEC=l.6121E-13************** ************** ● ************ ************** ***************
AL 26 (n,g) AL 27 (n, a) NA 24
AL 26 (n,g) AL 27 XSEC=2 .7f387E-13AL 27 (n,a) NA 24 XSEC=l .6121E-13************** ************** ************* ************** ****
***********
. . .
*************** ************** ************** ************** *************
MG26 (n, H) NE 24 (B-) NA 24
MG 26 (n, H) NE 24 XSEC=O. 0000E+OONE 24 (B-) NA 24 DELTA=3. 4179E-03*************** *************** *************** *************************MG 28 (n,na) NE 24 (B-) NA 24
xl
MG 28 (n,na) NE 24 XSEC=5.0353E-16NE 24 (B-) NA 24 DELTA=3.4179E-03
******JOB FINISHED******
Eachpathwayis listedalongwith thereaction(ts$) ordecay (k)probabilities pernucleus per unit time.
The second example demonstrates the operation of CHAINS in mode #2.
Example #2:
2 IFLAG130270 INITIAL Al-27110240 IFINAL Na-2440.1 PCNT
This input file will cause CHAINS to output all possible pathways for theproduction “Na from ‘Al that require up to 4 steps and contribute at least 0.1%to the total pseudo probability. An excerpt of the output from this problem isgiven below:
NUMBEROF ENCOUNTEREDCHAINS NCHAIN= 194NUMBEROF CHAINS WITH RELATIVE PROBABILITY HIGHER THANPCNT, NCH= 13TOTAL PROB.= 20.2428************** ************* ************** ************** ***************
P= 55.34AL 27 (n,a) NA 24
AL 27 (n,a) NA 24 XSEC=l .6121E-13************** ************* ************** *********”********************
P= 24.74
AL 27 (n,a-m) NA 24M(IT) NA 24
AL 27 (n,a-m) NA 24M XSEC=7 .2424E-14
NA 24M(1T) NA 24 DELTA= 3.4143E+01*************** ************** *************** ************** *
***********
P= 5.11
AL 27 (n,np) MG 26 (n,a) NE 23 (B-) NA 23 (n,g) NA
24
AL 27 (n,np) MG 26 XSEC=5 .2098E-13
MG 26 (n,a) NE 23 XSEC=1.5283E-13
. .
—... ......--------.=——=- . .... ..... .. -...—.---=/---------
NE 23 (B-) NA 23 DELTA=1.8633E-02NA 23 (n,g) NA 24 XSEC=2.4667E-13● ************ ************* ************* ************* *******
***********
P= 3.96
AL 27 (n,na) NA 23 (n,g-m) NA 24M(IT) NA 24
AL 27 (n,na) NA 23 XSEC=2.8631E-14NA 23 (n,g-m) NA 24M XSEC=7.3444E-13NA 24M(IT) NA 24 DELTA=3.4143E+OI************** ************* ************* ************* *****************
...
*************** ************** ************** ************** *************
P= 0.22
AL 27 (n,2n) AL 26 (n,a) NA 23 (n,g-m) NA 24M(IT) NA24
AL 27 (n,2n) AL 26. XSEC=l..7618E-14AL 26 (n,a) NA 23 XSEC=2.3787E-13NA 23 (n,g-m) NA 24M XSEC=7.3444E-13NA 24M(IT) NA 24 DELTA=3.4143E+01************** ************** ************** ************* ***************
P= 0.19
AL 27 (n,D) MG 26 (n,2n) MG 25 (n,2n) MG24 (n,p)24
NA
AL 27 (n,D) MG 26 XSEC=3.0214E-14MG 26 (n,2n) MG 25 XSEC=4.1518E-13MG 25 (n,2n) MG 24 XSEC=1.1279E-13
MG 24 (n,p) NA 24 XSEC=2.5837E-13
******JOB FINISHED******
Note that the first line of output indicates that atotalof 194 pathwaysthat result in the. production of24Na from ”Al within 4steps were identified.The second line of output indicates, however, that only 130f these possiblepathways makea contribution ofat least O.l% tothe total pseudo probability.!%weralofthesepathways are listedintheoutput above. Foreachpathway, thetotal percentage contribution to the total pseudo probability is given. This isfollowed byalisting ofthe pathway and the reactionordecay probabilities pernucleusperunit timeforeachstep inthepathway.
.....—.. .
The next example, that also addresses the operation of CHAINS in modenumber #2,is intended to show how the present version of CHAINS includesthe fission channel in the pathway analysis.
Example #3:
1 IFLAG922380 INITIAL U-238551370 IFINAL CS-13740.1 PCNT
Thisinputfilewillcause CHAINS to output all possible pathways for theproduction CS-137 from U-238 that require up to 4 steps and contribute at least0.1% to the total pseudo probability.
The complete output from this problem is given below:
MJ.kfBEROF ENCOUNTERED CHAINS NCHAIN =2327
NLMBER OF CHAINS WITH RELATIVE PROBABILITYHIGHER THAN, XCH= 4
;: PTOT=2.0273.-.
.*****.*.************************● **********● ****...******************
U238 (:, g) U239 (B-) NP239 (B-) IW239 (N,?) CS137
U238 (=,g) U239 XSEC=5.4317E-09tn39 (5-) NP239 DELTA=4 .9229E-04
~p~39 (~-) PU239 DELTA=3 .4061E-06pC239 {>,F) CS137 XSEC=2.6494E-10
. ..***...**** ● ☛☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☛☛☛☛ ● ☛ ☛ ☛☛☛☛☛☛✎☛☛ ☛✎✎☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☛
U238 (X,F) XE137 (B-) CS137
7J238 (>;,F) XE137 XSEC=l .2398E-12XE137 (5-) CS137 DELTA=3 .0255E-03
. *****..***** ● ☛☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☛☛☛☛ ☛✎☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☞
p. .64
U238 (N,F) 1136M(!3-) XE136 (n,g) XE137 (B-) CS137
U238 (N,F) 1136M XSEC=2 .7891E-121136M(B-) XE136 DELTA=l .5403E-02
xE136 (n,g) XE137 XSEC=7.4160E-12XE137 (B-) CS137 DELTA=3 .0255E-03
● ☛☛☛☛☛☛☛☛☛☛☛☞ ● ☞☛☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☛☛☛☛☛☛ ☛☛☛☛☛☛☛☞☛☛☛☛☛ ● ***’4******** *****
P= .30
U238 (N,F) 1136 (B-) XE136 (n,g) XE137 (B-) CS137
U238 (N,F) 1136 XSEC=1.3291E-121136 (B-) XE136 DELTA=8.2518E-03
XE136 (n,g) XE137 XSEC=7.4160E-12xE~37 (B-) CS137 DELTA=3.0255E-03
******JOB FINISHED******
Thefirudexample demonstratesthe operationofCHAINS inmode#3,
Example#4:
3 IFLAG110240 INITIAL Na-244
This example causes CHAINS to’ output all possible pathways for theproduction of“Na from an original2’Naatom. Allpathways thatrequireup to4
stepsaregiven.These are calledcyclicalpathways. An excerptof the output is
gi~~enbelow:
NUMBEROF ENCOUNTEREDCHAINS NCHAIN= 42
“*+****(--CL1C (-~IrJs******
************** ************* ************** ************** **********-k****
CHAINS WITH 2 LINKS************** ************* *****A******** ************* ****************
NA 24 (B-) MG 24 (n,p) NA 24
NA 24 (B-) MG 24 DELTA= 1.2853E-05
MG 24 (n,p) NA 24 XSEC=2 .5837E-13************** ************* ************** ************** ****
***********
NA 24 (n,2n) NA 23 (n,g) NA 24
NA 24 (n,2n) NA 23 XSEC=8 .1295E-13NA 23 (n,g) NA 24 XSEC=2 .4667E-13*******x****** ************* ************** ************** ***************
NA 24 (n, n’) NA 24 M(IT) NA 24
NA 24 (n,n’) NA 24M XSEC=3 .5792E-13
NA 24M(IT) NA 24 DELTA=3 .4143E+01.
x5
.....—.- ....-----.-.+.
************** ************* ************** ************** ***************
NA 24 (n,p) NE 24 (B-) NA 24
NA 24 (n,p) NE 24 XSEC=6 .1945E-14
NE 24 (B-) NA 24 DELTA=3 .4179E-03************** ************* ************** ************** ***************
CHAINS WITH 3 LINKS************** ************* ************** ************** ***************
NA 24 (B-) MG 24 (n,g) MG 25 (n,D) NA 24
NA 24 (B-) MG 24 DELTA= 1.2853E-05MG 24 (n,g) MG 25 XSEC=9 .8661E-14MG 25 (n,D) NA 24 XSEC=1.3629E-14****-*********************** ************** ● ************* ***************
NA 24 (n,g) NA 25 (B-) MG 25 (n,D) NA 24
NA 24 (n,g) NA 25 XSEC=5.9161E-14NA 25 (B-) MG 25 DELTA=l.1630E-02... MG25 (ri,D) NA 24 XSEC=1.3629E-14*************** ************** *************** ************** ************
. . .
*************** ************** *************** ***”*********** *
***********
CHAINS WITH 4 LINKS************** ************* ************** ************** ****
******7’****
NA 24 (B-) MG 24 (n,g) MG 25 (n,g) MG 26 (n,T) NA24
NA 24 (B-) MG 24 DELTA=1.2853E-05MG 24 (n,g) MG 25 XSEC=9.8661E-14MG 25 (n,g) MG 26 XSEC=3.5518E-13MG 26 (n,T) NA 24 XSEC=O.OOOOE+OO************** ************* **+*********** ************** ***************
NA 24 (n,g) NA 25 (B-) MG 25 (n,g) MG 26 (n,T) NA24
NA 24 (n,g) NA 25 XSEC=5.9161E-14NA 25 (B-) MG 25 DELTA=1.1630E-02MG 25 (n,g) MG 26 XSEC=3.5518E-13MG 26 (n,T) NA 24 XSEC=o.OoOOE+OO************** ************** ************** ************** **************
M
NA 24 (n,n’). NA 24M(B-) MG 24 (n,g) MG 25 (n,D) NA24
NA 24 (n,n’) NA 24M XSEC=3.5792E-13NA 24M(B-) MG 24 DELTA= 1.7157E-01
MG 24 (n,g) MG 25 XSEC=9.8661E-14
MG 25 (n,D) NA 24 XSEC=1.3629E-14*************** ************** ************** ************** *************
. . . .
The first hneofoutputi ndicates thata total of 42 pathways were identified.Note,however,that the firsttwopathwayi with4stepsboth endwiththeXMg(n,t)’’Na reaction. Thisreactionhas anenergy-averaged cross sectionofO barns(the threshold is14.7 MeVbut theflux isOabove14.lMeV). Whenoperatedinmode#3,CHAINS makesno attempt to extract possible pathways that will notcontribute to the overall production.
CHAINS AvailabilityThe CHAINS utility currently operates on Crays and an HP/735
workstations. As is ACAB, CHAINS is written in standard FORTRAN 77. Thus,porting of CHAINS onto other machines should not be difficult.
x7
IX.- References.
1.-A.G. Croff, A User’s Manual for the 0RIGEN2 computer code. ORNL/TM-7175,1980.
2.-H. Brockmann and U. Ohling, ACFA: A General Purpose ActizMion Code,Jiilich 1866,1983.
3.- E.T. Cheng, R.A. Forrest and A. Paschenko, Report on the Second InternationalActivationCizlczdationBenchmark ComparisonStudy, TSI Research Report TSIR-21FINAL Draft, 1993.
4.-J. Sanz, J.M. Perlado, D. Guerra, S. P&ez, J. Latkowski, M- Tobin, ACAB,ActivationCodefor Fusion Applications User’s Manual V2.0, Lawrence LivermoreNaticmal Laboratory, UCRL-MA-122002, August 1995.
5.- A.B. Pashchenko, H. Wienkle, J. Kopecky, J. Chu. Sublet, R.A. Forrrest,FENDL/A-2.0, Neutron activation cross section data libraryfor jision applications.Version 1 q~March 1996. International Atomic Energy Agency IAEA-NDS-173,Presented at the IAEA Advisory Group Meeting, FENDL-2, Vienna, March1997.
6.-R.A. Forrest, FEiVDL/D-2.Oand testing of FENDVA-2.O. Presented at the IAEAAdvisory Group Meeting, FENDL-2 Vienna, March 1997.
7.-Summary Report of the /EF Working Group on Benchmark Testing, DataProcessingnnd Evaluation,NEA Paris, 12th-13th June 1995, Report JEF/DOC-538,Ph. Finck (Chairman, CEN Cadarache), M. Konieczny (Secretary, NEA DataBank),
8.- J. Kopecky and D. Nierop, The European Activation File EAF-4. Summarydocumenh~tion.ECN-C-95-072. December 1995.
9.- Summary report of the IAEA Specialists’ Meeting on Extension andImprovementof the FENDL Libray for Fusion Applications(FENDL-2). Vienna, 3-7March 1997, Report INDC (NDS)-373, July 1997, prepared by M. Herman andA.B. Pashchenko.
10.- Proc. 3rd RCM on Activation cross sections for the geration of long-livedradionuchdes of importance in -fusion reactor technology, St. Petersburg, Russi~,June 19-23, 1995, IAEA Report INDC (NDS)-342, Feb. 1996. A.T3.Pashchenko,Ed.
11.- J. Kopecky et al., The European File EAF-3 with Neutron Activation andTransmutationCross-Sections,Netherlands Energy Researach Foundation. ReportECN-C-92-058, 1992.
till
—......-.-= ....4.........-b.......=........ —-.. ......
12.- J.F.Latkowsky, Inertia/ Fusion Energy: A Clearer view of the safety andenvironmentfzl perspectives. PhD dissertation, University of California atBerkeley, May 1996. UCRL-LR-125741, November 1996.
13.- R.W. Moir etal.,HYLIFE-11: A molten-saltinertialfusion energy power plantdesign-FinalReport.Fusion Technology, 25,5-25,1994.
14.-S.Fetter,E.T.Cheng and F-M. Mann, Long-term radioactive waste from fusionreactors:Part H, Fusion Eng. Des., 13,239,1990.
15.- J. Sanz, C. Gonz&lez, J. Juan, Long-lived activity of elements: effect of newactivationcross sections and their uncertainties on the selection of materialsfor lFEreactors,to be presented on the 8th International Conference on Fusion ReactorMaterials, ICFRM-8, Sendai, Japan, October 1997.
16.- J.K. Tuli, Nuclear Wallet Cards (Fifth edition), National Nuclear Data Center,Brookhaven National Laboratory, July 1995.
17.- J.H. Hubbell, Photon Mass Attenuation and Energy-Absorption Coefficientsfrom 1 keV to20 MeV, Int. J. Appli. Radiat. Isot., 33,1982.
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.. ... .. . .—
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