ongoing work and goals of the nuclear data team · tmc applied to burn-up calculations with serpent...
TRANSCRIPT
1 / 31
Ongoing work and goals of the
nuclear data team
D. Rochman and A.J. Koning
Nuclear Research and Consultancy Group,
NRG, Petten, The Netherlands
Uppsala, Sweden, November 2011
Contents
2 / 31
① Method of work
② Applications: TMC, TENDL, TMC−1
③ Conclusions
A (very) brief and recent history of nuclear data in NRG
3 / 31
1997 2000 2003 2006 2009 2012
1st idea of
TALYS
TENDL
TMC
T6
Inverse
TMC
Manhattan-2
project
TALYS-1.0
released
TENDL-2011
released
TENDL-2010
released
TENDL-2009
released
TALYS-1.2
released
TENDL-2008
released
Backbone of our methodology: REPRODUCIBILITY
4 / 31
TALYSnuclear code
T6 softwarepackage
Librarycloning andcomplement ReproducibilityN
RG
Nuc
le
ardata team
Original nuclear datalibrary TENDL+ covariances
Uncertaintypropagation
TMC
OptimumSearch and find(Inverse TMC)
TMC: Total Monte Carlo
5 / 31
Uncertaintypropagation
TMC
• Started in 2008
• Many publications
• Applied to crit-saf and shielding benchmarks, reactor (keff, βeff, void,Doppler), burn-up inventory, radiotoxicity
• Still a controversial method
TMC: procedure for the random file production
6 / 31
AutoTalysTASMAN
n TANESinput files
n TALYSinput files
n TARESinput files
n TAFISinput files
TANES TALYS TARES TAFIS
n FissionNeutron Spect.
output files
n TALYSoutput files
n ResonanceParametersoutput files
n ν-baroutput files
TEFAL
1 ENDF file+
covariancesn×
ENDFrandom files
TMC: Total Monte Carlo
7 / 31
Control of nuclear data (TALYS)+ simple processing (NJOY)
+ system simulation (MCNP/ERANOS/CASMO...)
1000times
For each random ENDF file, the benchmark calculation is performed withMCNP. At the end of the n calculations, n different keff values are obtained. In theobtained probability distribution of keff, the standard deviation σtotal reflects twodifferent effects: σ2
total = σ2statistics +σ2
nuclear data.
hst1-1 (236U)
keff value
Num
ber
ofco
unts
/bin
s
1.0020.9990.9960.993
40
30
20
10
0
Examples with 63Cu(n,2n) and 65Cu(n,el)
8 / 31
n = 10063Cu(n,2n)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
2018161412
1.0
0.8
0.6
0.4
0.2
0.0
n = 163Cu(n,2n)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
2018161412
1.0
0.8
0.6
0.4
0.2
0.0
Skewness = 0.33
Sigma = 4 mb/Sr
Mean = 22 mb/Sr
cos(θ) = −0.41
En = 8 MeV65Cu(n,el)
Cross section (b/Sr)
Cou
nts
/bin
0.050.040.030.020.01
20
15
10
5
0
En = 8 MeV
65Cu(n,el) (n=100)
cos(θ)
dσ/d
θ(b
/Sr)
0.80.50.2-0.1-0.4-0.7-1.0
101
100
10−1
10−2
Nuclear data: examples on (n,2n) cross sections
9 / 31
Exp.ENDF/B-VII.0
This work
100 random 241Am(n,2n)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
bar
ns)
2015105
600
400
200
0Exp.
ENDF/B-VII.0This work
100 random 232Th(n,2n)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(b
arns)
2015105
3
2
1
0
Exp.ENDF/B-VII.0
This work
100 random 235U(n,2n)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
bar
ns)
2015105
1200
800
400
0
Exp.ENDF/B-VII.0
This work
100 random 239Pu(n,2n)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
bar
ns)
2015105
600
400
200
0
Nuclear data: examples in the resonance region
10 / 31
JEFF-3.1ENDF/B-VII.0
This workExp
50 random 241Pu(n,f)
Incident neutron energy (eV)
Cro
ssse
ctio
n(b
arns)
10010−110−2
104
103
102
101
JEFF-3.1ENDF/B-VII.0
This workExp
50 random 235U(n,f)
Incident neutron energy (eV)
Cro
ssse
ctio
n(b
arns)
4.03.02.01.00.40.1
102
101
TMC applied to a SFR void coefficient
11 / 31
Reduced Chi-square=0.215
SVR= 8.02510± 0.55092 $
Kalimer void coefficient (23Na)
Void coefficient value ($)
Num
ber
ofco
unts
/bin
s
9.38.77.97.36.7
20
15
10
5
0<Skewness>
Sample number
Updat
edsk
ewnes
s
8006004002000
0.0
-0.1
-0.2
-0.3
-0.4
< σ >
Updat
edunce
rtai
nty
($)
0.6
0.5
0.4
0.3
< void coefficient >
Sodium Fast Reactor (Kalimer-600)
Updat
edSV
R($
)
8.5
8.3
8.1
7.9
TMC applied to shielding benchmark (Mn Oktavian benchmark)
12 / 31
Emission Gamma Energy (MeV)
25
15
5
10532
Emission Neutron Energy (MeV)
Unce
rtai
nty
(%)
10.05.03.01.00.5
3020100
ExperimentJEFF-3.1This work
Oktavian 55Mn Neutron Leakage
Lea
kage
curr
ent/
leth
argy
/sou
rce
par
ticl
e 0.60
0.30
0.20
0.10
0.05
ExperimentJEFF-3.1This work
Oktavian 55Mn Gamma Leakage
0.100
0.050
0.010
0.005
0.001
TMC applied to burn-up calculations with SERPENT
13 / 31
PWR fuel element based on a Westinghouse 3-loop PWR design (array of 17x17),4 m in length, 21.5 cm in width, 400-500 kg of enriched uranium (4.8 % in 235U)
due to fission yieldsdue to transport data
238U+235U+239Pu
Burn up (GWd/tHM)
Unce
rtai
nty
onk
eff(%
)
6050403020100
2.0
1.5
1.0
0.5
0.0
due to fission yieldsdue to transport data
239Pu
Burn up (GWd/tHM)
Uncertain
tyon
keff
(%)
1.5
1.0
0.5
0.06050403020100
due to fission yieldsdue to transport data
235U
Burn up (GWd/tHM)
Uncertain
tyon
keff
(%)
1.5
1.0
0.5
0.0605040302010
Unce
rtai
nty
onk
eff(%
) 1.5
1.0
0.5
0.0
due to decay Datadue to fission yields
due to transport data
238U
Burn up (GWd/tHM)605040302010
TMC applied to burn-up calculations with DRAGON
14 / 31
Unce
rtai
nty
onk
eff(%
) 1.0
0.8
0.6
0.4
0.2
0.0
due to transport data
238U
Burn up (GWd/tHM)605040302010
due to nu-bardue to pointwise xsdue to resonance xs
due to transport data
238U
Burn up (GWd/tHM)
Unce
rtai
nty
onk
eff(%
)
6050403020100
1.0
0.8
0.6
0.4
0.2
0.0
SERPENT (Monte Carlo) DRAGON (deterministic)
TENDL: nuclear data production
15 / 31
Librarycloning andcomplement
Original nuclear datalibrary TENDL+ covariances
• Started in 2008
• TENDL libraries released every year
• First of its kind by the method of production
• First of its kind by separating evaluation work and library production
• ' 80 isotopes from TENDL to JEFF-3.2β, to FENDL
TENDL: Motivations
16 / 31
We need a consistent and complete nuclear data library to be integrated in reactorcalculations, including realistic covariance data.
(None of the existing libraries fulfill these requirements.)
� Use global, robust TALYS method for the bulk of nuclides,
� Use in-depth evaluation, adjustment... for important nuclides (e.g. 56Fe,239Pu),
� Reproducible library,
� ENDF, PENDF, ACE, EAF and text format,
� Available at www.talys.eu/tendl-2008 (2009, 2010 and 2011).
Produce TENDL-2008, -2009, -2010 ... with an increasing quality with regard to:differential data, model development, integral validation, completeness andcovariance data
TENDL: Standard and modern approaches
17 / 31
ManualCross section
evaluation
(semi) ManualFormatting
• Manual validation• Manual Feedback
JEFF, ENDF/B, JENDL...
ManualCross section
evaluation
AutomaticFormatting
• Automatic validation• Manual Feedback
TENDL
TENDL-2011: t1/2 > 1 sec, 200 MeV (n, p, d, t, a, γ reactions)
18 / 31
TENDL cloning of other library
19 / 31
When TALYS can not reproduce experimental cross sections, normalization isapplied
TALYS-1.2ENDF/B-VII.0
Exp.
238U(n,f)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(b
)
1815129630
1.5
1
0.5
0
TENDL cloning of other library
19 / 31
When TALYS can not reproduce experimental cross sections, normalization isapplied
TENDL-2010TALYS-1.2
ENDF/B-VII.0Exp.
238U(n,f)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(b
)
1815129630
1.5
1
0.5
0
Monte Carlo Nuclear Data Adjustment: TMC−1
20 / 31
OptimumSearch and find(Inverse TMC)
• Started in 2010
• Two publications so far
• Controversial (if understood at all)
• We believe this is the future of nuclear data evaluation work
• It might be the only way to sensibly improve C/E
Inverse TMC on 239Pu
21 / 31
Total Monte Carlo + selection=⇒ 1
TMC
① Use TALYS to create a single 239Pu evaluation close or equal toENDF/B-VII.0 or JEFF-3.1.1
② Randomize all model parameters (resonances, nubar, fission neutronspectrum, TALYS parameters) to create 500 random 239Pu evaluations
③ Benchmarks the n ≥ 500 files with the same set of criticality benchmarks
④ Select the best random file
Example: 100 benchmarks, 500 random files =⇒ 500 TALYS + NJOY and 100×500 = 5 ·104 MCNP loops,1.4 years on a single processor, or 5 days on 100 processors (3 GHz)
Inverse TMC: simple example with 6 keff benchmarks
22 / 31
JEFF-3.1 & ENDF/B-VII.0
TENDL-2009JENDL-3.3 & CENDL-3
ENDF/B-VI.8
Jezebel (pmf1) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
TENDL-2009
JEFF-3.1ENDF/B-VII.0
Jezebel-240 (pmf2) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf12 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf5 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pst1-6 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
Thor (pmf8) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
αJEFF-3.1.1: 1.14e−4
JENDL-3.3: 1.71e−4
TENDL-2009: 3.66e−4
ENDF/B-VI.8: 1.72e−4
ENDF/B-VII.0: 1.69e−4
α = ∑ni=0
(Ci−Ei)2
Ci,
Inverse TMC: simple example with 6 keff benchmarks
22 / 31
JEFF-3.1 & ENDF/B-VII.0
TENDL-2009JENDL-3.3 & CENDL-3
ENDF/B-VI.8
Jezebel (pmf1) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
TENDL-2009
JEFF-3.1ENDF/B-VII.0
Jezebel-240 (pmf2) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf12 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf5 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pst1-6 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
Thor (pmf8) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
αJEFF-3.1.1: 1.14e−4
JENDL-3.3: 1.71e−4
TENDL-2009: 3.66e−4
ENDF/B-VI.8: 1.72e−4
ENDF/B-VII.0: 1.69e−4
random 0: 2.29e−4
random 1: 13.4e−4
Inverse TMC: 6 keff benchmarks with random 239Pu
23 / 31
JEFF-3.1 & ENDF/B-VII.0
TENDL-2009JENDL-3.3 & CENDL-3
ENDF/B-VI.8
Jezebel (pmf1) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
TENDL-2009
JEFF-3.1ENDF/B-VII.0
Jezebel-240 (pmf2) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf12 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pmf5 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
pst1-6 keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
Thor (pmf8) keff
keff value
Num
ber
ofco
unts
/bin
s
1.0201.0101.0000.9900.980
10
5
0
αJEFF-3.1.1: 1.14e−4
JENDL-3.3: 1.71e−4
TENDL-2009: 3.66e−4
ENDF/B-VI.8: 1.72e−4
ENDF/B-VII.0: 1.69e−4
Real case: 120 239Pu benchmarks
24 / 31
Table 1: List of plutonium benchmarks selected for the random search.
Name Cases Name Cases Name Cases Name Casespmf1 1 pmf2 1 pmf5 1 pmf6 1pmf8 1 pmf12 1 pmf13 1 pci1 1pmi2 1 pst1 6 pst2 6 pst3 8pst4 13 pst5 9 pst6 3 pst7 9pst8 29 pst12 22 pmm1 6
α =n
∑i=0
(Ci −Ei)2
Ci, (1)
Results independent of the type of factor α, χ2... or
F = 1−10√
1N ∑(log(Ei)−log(Ci))
2(2)
α values for random 239Pu evaluations
25 / 31
RandomJEFF-3.1
JENDL-3.3ENDF/B-VI.8
ENDF/B-VII.0
Random file number
αper
random
file
7006005004003002001000
1· 10−1
2· 10−2
5· 10−3
C/E values for the best 239Pu (run 307)
26 / 31
Run 307 (α = 0.0048)JEFF-3.1 (α = 0.0081)
Benchmark239Pu benchmarks
Benchmark type
C/E
pmm
1-6
pmm
1-1
pst1
2-19
pst1
2-14
pst1
2-9
pst1
2-4
pst8
-28
pst8
-23
pst8
-18
pst8
-13
pst8
-8
pst8
-2
pst7
-7
pst6
-3
pst5
-7
pst5
-2
pst4
-10
pst4
-5
pst3
-8
pst3
-3
pst2
-5
pst1
-5
pmi2
-1
pmf8
pmf1
1.04
1.02
1.00
Inverse TMC: best 239Pu for the ANDES project
27 / 31
NRG 95Mo, 56Fe, 239Pu, 28Si, 182W + JEFF-3.1JEFF-3.1
ENDFB/-VII.1Benchmarks
239Pu fast benchmarks
September 15, 2011 at 15:41
Benchmark type
C/E
pst1
-1
mcf
4
mcf
3-2
mcf
3-1
mcf
2
mcf
1
pmm
1-6
pmm
1-5
pmm
1-4
pmm
1-3
pmm
1-2
pmm
1-1
pmi2
pci1
pmf1
3
pmf1
2
pmf8
pmf6
pmf5
pmf2
pmf1
1.015
1.010
1.005
1.000
0.995
Inverse TMC: second example on natural copper and Oktavianbenchmark
28 / 31
ExperimentJEFF-3.1This work
Emission Neutron Energy (MeV)
Lea
kage
curr
ent/
leth
argy
/sou
rce
par
ticl
e
Lea
kage
curr
ent/
leth
argy
/sou
rce
par
ticl
e
10532
0.30
0.20
0.10
0.05
0.02
ExperimentJEFF-3.1This work
Emission Gamma Energy (MeV)
Lea
kage
curr
ent/
leth
argy
/sou
rce
par
ticl
e
0.05
0.02
0.01
0.01
10532
Software release: TALYS and T6
29 / 31
TALYSnuclear code
T6 softwarepackage
• TALYS: latest release in December 2012,
• T6: started 2011,
• T6: ”(almost) all our knowledge in a tar file”
• with T6, anyone can produce ENDF evaluations, ACE files, random files,TENDLs...
Software release: T6
30 / 31
t6.tar(a tar file)
TALYS TASMAN TEFAL TARES TANES TAFISTools
autotalys NJOY? PREPRO libs checkingtools acedit
t6 tested on many systems (Linux RedHat, Ubuntu, FreeBSD),with many compilers (g95, gfortran, ifort, lf95, g++, Intel C++)
from Li to Cf, from 0 to 200 MeV?: if authorized
Future work
31 / 31
➪ Continue with TMC (more reactor calculations, applied to current reactors),
➪ Improve the quality of the TENDL library,
1. in format (new needs or existing problems)2. in cross sections (better fit to differential and integral data)
➪ Apply TMC−1 to a large number of isotope (including crit-safety, reactor,dosimetry benchmarks)
➪ Release T6 (or part of it) ?
, And finally world domination (and world peace).