Physor 2012 D. Rochman – 1 / 16
TENDL-2011:TALYS-based Evaluated Nuclear Data Library
D. Rochman and A.J. Koning
Nuclear Research and Consultancy Group,
NRG, Petten, The Netherlands
J.-C. Sublet
United Kingdom Atomic Energy Authority, U.K.
PHYSOR conference, Knoxville, USA, April 2012
Motivations
Physor 2012D. Rochman – 2 / 16
We need aconsistent and completenuclear 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
Produce TENDL-2008, -2009, -2010... with an increasing quality with regard to:differential data, model development, integral validation, completeness and covariancedata
Standard and modern approaches
Physor 2012D. Rochman – 3 / 16
ManualCross section
evaluation
(semi) ManualFormatting
• Manual validation• Manual Feedback
JEFF, ENDF/B, JENDL...
Standard and modern approaches
Physor 2012D. Rochman – 3 / 16
ManualCross section
evaluation
(semi) ManualFormatting
• Manual validation• Manual Feedback
JEFF, ENDF/B, JENDL...
ManualCross section
evaluation
AutomaticFormatting
• Automatic validation• Manual Feedback
TENDL
Nuclear data file evaluation and production with the TALYS system.
Physor 2012D. Rochman – 4 / 16
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
Possible outcomes based on the TALYS system
Physor 2012D. Rochman – 5 / 16
TALYSnuclear code
T6 softwarepackage
Librarycloning andcomplement ReproducibilityN
RG
Nuc
le
ardata team
Original nuclear datalibrary TENDL+ covariances
Uncertaintypropagation
TMC
OptimumSearch and find(Inverse TMC)
Content 1- TENDL-2011
Physor 2012D. Rochman – 6 / 16
� Available at www.talys.eu/tendl-2011� Neutrons: ENDF files (MF1-15 and MF31-35), plots, ACE, EAF, processed files
andrandomfiles (do your own Total Monte Carlo)� Protons, deuterons, tritons, alphas, gammas: ENDF, ACE, EAF files� Based on TALYS +automatic normalization
Neu
tron
Pro
ton
Deu
tero
n
Trito
n
Alp
ha
Heliu
m3
Phot
on
Fi.
Yield
s
TENDL-2011 2425 2429 2419 2431 2429 2428 2428 574
TENDL-2010 2394 1157 1159 1156 1159 1140 1152 529
TENDL-2009 2375 1163 1164 1116 1163 1127 1165 509
TENDL-2008 348 344 336 339 342 338 327
(JEFF-3.1) 381 26 44(ENDF/B-VII.0) 393 48 5 3 163 80
Content 2- TENDL-2011 Neutron library: 19F to 281Ds (t1/2 > 1 sec)
Physor 2012D. Rochman – 7 / 16
Default Calculations Medium Quality Better QualityActivation Quality
Nucl
ear
Char
geZ
0
8
16
24
32
40
48
56
64
72
80
88
96
104
112
120
0 13 26 39 52 65 78 91 104 117 130 143 156 169 182 195 208 221 234 247 260 273 286 299 312
TENDL-2010
JEFF-3.1 (shifted + 50 A)
Fe 46-66
Pb 180-241
Pu 229-247
Content 3- Available files
Physor 2012D. Rochman – 8 / 16
❶ Tabular angular distributions❷ Tabular Gamma-ray intensities❸ Tabular partial cross sections to discrete levels❹ Tabular residual cross sections❺ Tabular cross sections❻ ENDF files including covariances❼ EAF cross section and variance files❽ ProcessedACE files (with NJOY)❾ Processed covariances (tabular and plots)
Content 4- TENDL-2011 Neutron library: from MF-1 to MF-35
Physor 2012D. Rochman – 9 / 16
Content of a typical file up to200 MeV:
☞ MF-1: Description + fission parameters☞ MF-2: Resonance parameters (Reich-Moore or Multi-level Breit Wigner)☞ MF-3: Cross sections (n,tot), (n,el), (n,non), (n,inli), ..., (n,γ), (n,pi), (n,αi)☞ MF-4: Elastic angular distribution (Legendre Polynomials)☞ MF-5: Fission neutron spectrum☞ MF-6: Double differential distributions and spectra for (n,2n), ..., (n,αi)☞ MF- 8-10: Isomeric cross sections☞ MF- 12-15: Gamma yields, angular distributions and spectra☞ MF- 31-32-33-34-35: nubar, Resonance parameter, cross section, elastic angular
distribution and fission neutron spectrum covariances
Examples: Some actinides of TENDL-2011
Physor 2012D. Rochman – 10 / 16
TENDL-2010random 238U(n,f)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
1010.1
1.5
1.0
0.5
0.0
TENDL-2010random
235U(n,f)2
1
TENDL-2010random
239Pu(n,f)
3
2
1
Examples 5: TENDL-2011 adjusted for activation
Physor 2012D. Rochman – 11 / 16
ENDF/B-VII.0TENDL-2010
Exp.
63Cu(n,2n)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(b
)
201816141210
1
0.5
0
JEFF-3.1IRDF-2002
TENDL-2010Exp.
63Cu(n,α)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
b)
1684
50
0
ENDF/B-VII.0IRDF-2002
TENDL-2010Exp.
27Al(n,p)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
b)
16842
200
100
0
IRDF-2002TENDL-2010
Exp.27Al(n,α)
Incident neutron energy (MeV)
Cro
ssse
ctio
n(m
b)
321684
200
100
0
TENDL-2011: validation
Physor 2012D. Rochman – 12 / 16
Table 1: C/E ICSBEP benchmarks calculated with TRIPOLI.
Benchmarks JEFF-3.1.2 ENDF/B-VII.1 TENDL-2011IMF-7 (BigTen) detailed 0.99430 1.00028 0.99824IMF-7 (BigTen) simple 0.99323 1.00076 0.99746IMF-12 (ZPR-16 %) 1.00191 1.00299 1.00916IMF-10 (ZPR-9 %) 0.99649 1.00170 0.99900IMF-2 0.99207 0.99912 1.00083
Covariance examples
Physor 2012D. Rochman – 13 / 16
Current and future (next year) partnerships
Physor 2012D. Rochman – 14 / 16
FENDL-3 JEFF-3.2 EAF-2010
MCNPXSERPENT
Burn-up credit
TENDL libraries
+TMC
ActinidesANDES-EU
MCNP/FISPACTJRC-GRS
IFMIFUPM-UNED
MACROUppsala/Vattenfall
MCNPBurn-up credit
AREVA
GEN-IV
Fusion Reactor Uncertainties Reactor Uncertainties
Safety
Reactor Uncertainties
FusionReactor DevelopmentFusion
Radiation Transport
TENDL ”clicks”
Physor 2012D. Rochman – 15 / 16
TENDL-2011
TENDL-2010
TENDL-2009
TENDL-2008
TALYS 1.2
TALYS 1.0
hits per month at www.talys.eu
Time (month/year)
hit
s/m
onth
07/1201/1207/1101/1107/1001/1007/0901/0907/0801/0807/0701/0707/06
1· 105
1· 105
8· 104
6· 104
4· 104
2· 104
0· 100
Conclusions and Future improvements
Physor 2012D. Rochman – 16 / 16
☞ Consistent, complete data files with automatic updates for all nuclides, projectiles,energies reaction channels and quantities,
☞ Includes 315 URRs, random files☞ Detailed TALYS and resonance parameter fitting per individual isotope
Release date: December 28th, 2011
☛ Possibility to adopt an entire existing data library (e.g. JEFF-3.1.1) andmake itcomplete
☛ More extensive validation (burn-up...) with uncertainties☛ Improve global model and uncertainties, Addition of original URR