TENDL-2011: TALYS-based Evaluated Nuclear Data Library

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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

Transcript of TENDL-2011: TALYS-based Evaluated Nuclear Data Library

Page 1: TENDL-2011: TALYS-based Evaluated Nuclear Data Library

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

Page 2: TENDL-2011: TALYS-based Evaluated Nuclear Data Library

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

Page 3: TENDL-2011: TALYS-based Evaluated Nuclear Data Library

Standard and modern approaches

Physor 2012D. Rochman – 3 / 16

ManualCross section

evaluation

(semi) ManualFormatting

• Manual validation• Manual Feedback

JEFF, ENDF/B, JENDL...

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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

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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

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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)

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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

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Content 2- TENDL-2011 Neutron library: 19F to 281Ds (t1/2 > 1 sec)

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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

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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)

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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

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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

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Examples 5: TENDL-2011 adjusted for activation

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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

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TENDL-2011: validation

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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

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Covariance examples

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Current and future (next year) partnerships

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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

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TENDL ”clicks”

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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

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Conclusions and Future improvements

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☞ 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