tendl applications libraries - serpentmontecarlo.vtt.fi/mtg/fusion_2015/lee_morgan1.pdf · 2015. 6....

CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority.This work was funded by the RCUK Energy Programme [grant number EP/I501045] .

TENDL applications libraries

Lee Morgan, Michael Fleming

& Jean-Christophe Sublet

Culham Centre for Fusion Energy

1. The need for TENDL in fusion

2. TENDL Processing Methodology

3. Summary

Overview

Slide 2

Monte Carlo for Fusion Workshop – Cambridge University, 11-12th June 2015

Currently:

• 14 MeV fusion neutrons open up significantly more reaction channels than typically found in fission

• Experimentally derived nuclear data used for fusion modelling is:

– fragmented and incomplete

– expensive and slow to produce

– lacking in terms of uncertainty quantification

With TENDL:

• Comprehensive nuclear data upto 200 MeV

• Production of nuclear data libraries is relatively fast and cheap to produce

• Full covariance data available ( for codes that handle it)

The need for TENDL in fusion

Slide 3



Max

cross

sect

ion (

b)

Asymmetry (s)

1E-03

1E+01

1E-02

1E-01

1E+00

0.00 0.05 0.10 0.15 0.20 0.25

C/E

Neutron Spectrum

C/E = 0.9504

C/E = 1.0436

C/E = 0.9722

C/E = 1.0833

C/E = 0.9669C/E = 0.9422

C/E = 1.0302

C/E = 0.9926C/E = 0.9949

C/E = 1.1032C/E = 1.1150

C/E = 1.1645

C/E = 0.9806

C/E = 1.0208

C/E = 1.0569

C/E = 1.2776

1.10

0.91

0.70

0.90

1.10

1.30

1.50

sneg_2 fng_f82h.asc cf252_flux_1 cf252_flux_1 cf252_flux_1 fzk_ss316 fng_vanad.asc rez_DF

sneg_1 fzk_2 fns_7hour cf252_flux_1 cf252_flux_1 fzk_ss316 fzk_1 fng_eurofer.asc

Y-89(n,2n)Y-88

Final

Cro

ss s

ectio

n (

b)

Energy (eV)

0.0E+00

3.0E-01

6.0E-01

9.0E-01

1.2E+00

1.5E+00

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmPAT79RI 99KGU00LAS75KYU79MOH84ANL87BRC81LAS75KOS81FEI89FEI89SAV98BRC02RI 99LAS75AUB76JAE93LAS77AEP89

Validation: SACS

V&V, C/E integral anddifferential with uncertainty

• 2630 (2434) targets (H1 to Ds281)• Cross section, 90 reaction types

• Decay data: 3873 nuclides; 24 types• Stables and isomeric states; g, m, n, o,..

a, g, n, p, d-TENDL-2014 (-2013)

a, g, n, p, d-TENDL-2014 (-2013)

UKFY-4.2fission yieldUKFY-4.2fission yield

Decay-2012 Decay-2012

Hazard indicesHazard indices

CovarianceCovariance

ENDF/B, JENDL, JEFF

ENDF/B, JENDL, JEFF

Target x 3 Decay x 1.7

EASY-II &TENDL-2014, -2013

4

TENDL PROCESSING METHODOLOGY


• TENDL14 contains nuclear data for 2633 nuclides– Perfect to serve the needs of all aspects the nuclear community, however it is bulky and not

all nuclides are required for reactor applications– Hence, a reduced TENDL14_Lite nuclide index is required which contains only the nuclides

required for fusion/fission modelling

• Nuclide index list– JENDL (406)– ENDFB7.1 (423)– JEFF32 (472)

• TENDL14_Lite nuclide index set is created from the union of the JENDL, ENDF and JEFF nuclide sets– TENDL_Lite ( 496)

• The TENDL14_Lite nuclide index set is then split into N separate files, in order to run each set through NJOY in parallel.

TENDL PROCESSING METHODOLOGY STEP 1: REDUCED NUCLIDE INDEX SET

Slide 6


ASCIITENDL

file

MODER

RECONR Temp(RENDF)

BROADR

BINARYTENDL

file

UNRESR temp

Temp

TENDF

GASPR

HEATR

temp

THERMR temp

PURRBINARY PENDF

MODERASCII

PENDF

temp

VIEWR GRAPH

Each nuclide in theindex list is proces-sed using the foll-owing NJOY proc-edure in order tocreate a PENDF file.

STEP 2: CREATE PENDF

Slide 7


ASCIITENDL

file

BINARYTENDL

file

GRAPH

Each nuclide in theindex list is proces-sed using the foll-owing NJOY proc-edure in order tocreate an ACE filefrom a PENDF.

ASCII PENDF

ACE file

VIEWR

ACER

XSDIR file

ACER

ACE fileMODER

TENDL PROCESSING METHODOLOGY STEP 3: CREATE ACE +XSDIR

Slide 8


TENDL PROCESSING METHODOLOGY

STEP 3b: Checking Data

Slide 9


• In order to reduce disk I/O and create a compact nuclear data library, a single large ACE file is created which is a concatenation of all single xsdir entries produced by NJOY.

– The TENDL14_Lite nuclide index set results a single ACE file with size of approximately 8 Gb.

– A script is used to detect all files with ‘.xsdir’ extensions in a particular directory

– The script reads each xsdir entry into a XSDIR object and rewrites a single concatenated xsdir file with Filename, access_route and address modified.

– ENDFB7 mass tables are used

TENDL PROCESSING METHODOLOGY STEP 4: CREATE SINGLE, CONCATENATED ACE + XSDIR

to be used by MCNP6

Slide 10


• Although MCNP6 and SERPENT both read ACE files, the xsdirfiles have a different format– Mass tables are not present in the SERPENT XSDIR, unlike MCNP

– MCNP allows a single concatenated XSDIR, whereas SERPENT requires individual xs files for each nuclide.

• Use xsdirconvert.pl utility, provided in the SERPENT package to covert MCNP-style xsdir to SERPENT-style xsdir.

TENDL PROCESSING METHODOLOGY STEP 4: CREATE XSDIR file to be used by SERPENT

Slide 11


TENDL PROCESSING METHODOLOGY STEP 4: Angular scattering in more detail

[1] T. Hutton, J.C. Sublet, L. Morgan & T.W. Leadbeater. Nuclear data for fusion: Validation of typicalpre-processing methods for radiation transport calculations, Fusion Engineering and Design, InPress.

Normalised probability distribution functionsf(μ, E) for the elastic scatter of neutrons from56Fe at 14.1 MeV (red) and natC at 2.0 MeV(blue) [1] ( Law 4 - equal probability 32 bin).

Top: Difference between the functional andhistogrammed distributions. Bottom: Coeffic-ients of variation for the histogram

• Law 61 specified in NJOY script in order to simulate scattering of neutronics as accurately as possible, which is important for shielding calculations.

Slide 12


• Each isotope in the TENDL library is regression tested individually

• A script runs a MCNP or SERPENT model of a sphere of a single isotope, for each isotope in the TENDL_lite index

• Each model is run for one minute– The output file is checked for error keywords and file size criteria

• A list of passed/failed isotopes is produced– Output files of error producing input files are kept, others are deleted

• Work on non-regression testing of nuclear libraries is ongoing.

TENDL PROCESSING METHODOLOGY STEP 5: Regression Tests

Slide 13


• The full TENDL-14 library contains nuclear data for 2633 nuclides. – Extensive but bulky!

• TENDL_Lite has been created based on the nuclides found in the most recent JEFF, JENDL and ENDF libraries.

• TENDL_Lite libraries have been produced to serve both MCNP6 and SERPENT2

• In order to faithfully perform MCNP and SERPENT fusion benchmarking, both codes should read exactly the same nuclear data

• TENDL libraries have been regression tested using MCNP6 and SERPENT2.

• Ideally, LAW 61 should be implemented in SERPENT-2 nuclear data libraries .

Summary

Slide 14



END OF SLIDES


Acknowledgements

This work was funded by the RCUK Energy Programme under GrantEP/I501045 and the European Communities under the contract of Associationbetween EURATOM and CCFE. The views and opinions expressed herein donot necessarily reflect those of the European Commission. To obtain furtherinformation on the data and models underlying this paper please [email protected].

• In terms of the NJOY input file the difference between LAW 4 and LAW 61is small

– Law 4 represents the distribution of outgoing particle angles with Nequiprobable channels ( N=32 for ACE).i.e. for each incident neutronoutgoing angle, μ i, a PDF exists which defines Ei’.

– LAW 61 represents the distribution of outgoing particles (E’,μ) with atabulated CDF.

• For fission analysis this will make little difference to the result, howeverthe impact for fusion may be of importance

This is the title of the slide and the date it was written

Slide 17

TENDL PROCESSING METHODOLOGY STEP 4: CREATE XSDIR

acer-21 -24 0 31 321 0 1 0.14 0/'Ace $isma[$c1] TENDL-2014‘$isma[$c2] 293.6/0 1//

acer-21 -24 0 31 321 0 1 0.14 0/'Ace $isma[$c1] TENDL-2014‘$isma[$c2] 293.6/1 1//LAW 4 LAW 61

tendl applications libraries - serpentmontecarlo.vtt.fi/mtg/fusion_2015/lee_morgan1.pdf · 2015. 6....

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