filling up fendl with an all-in-one nuclear data evaluation and validation system around talys arjan...

Filling up FENDL with an all-in-one nuclear data evaluation and validation system around TALYS

Arjan Koning

NRG Petten, The Netherlands

FENDL-3 meeting

March 23-26 2010, IAEA, Vienna

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Contents

• Introduction • The TALYS code system• Complete nuclear data libraries (TENDL)

- n, g, p, d, t, h and a, 2400 nuclides, 200 MeV- Uncertainties and covariance data

• Performance- Differential data- Integral data

• This meeting- What can TENDL do for FENDL?- What can FENDL do for TENDL?

• Conclusions

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Neutronics, activation and nuclear data for fusion

Monte Carlo calculational procedure specifically suitable for ITER/IFMIF/DEMO neutronics analyses

Many relevant parameters can be determined:

- Neutron flux distributions

- Gamma flux distributions

- Radiation dose in optical fibers + required shielding

- Dose rates in port cell

- Nuclear heating

- Other relevant response parameters

Activation issues:

- activity, radiotoxicity, gamma dose rate, decay heat

Complete and good quality transport and activation data libraries are essential for a full simulation of all these effects.

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Relative importance of regions of ITER

upper port plug

Contributions of:

equatorial port plug divertor port plug

neutron flux distributions

MCNP calculations (A. Hogenbirk, NRG)

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Loop over energies

and isotopes

PRE-EQUILIBRIUM

Exciton model

Partial densities

Kalbach systematic

Approx DSD

Angular distributionsCluster emissions

emission

Exciton model

Hauser-Feshbach

Fission cascade

Exclusive channels

Recoils

MULTIPLE EMISSIONSTRUCTURE

Abundances

Discrete levels

Deformations

Masses

Level densities

Resonances

Fission parameters

Radial matter dens.

OPTICAL MODEL

Phenomenologic

Local or global

Semi-Microscopic

Tabulated

(ECIS)

DIRECT REACTION

Spherical / DWBA

Deformed / Coupled channel

Giant Resonances

Pickup, stripping, exchange

RotationalVibrational

COMPOUND

Hauser-Feshbach

Fluctuations

Fission Emission

Level densitiesGC + IgnatyukTabulatedSuperfluid ModelINPUT

projectile n

element Fe

mass 56

energy 0.1.

TALYS code schemeTALYS code scheme

OUTPUT

Spectra

XS

ENDF

Fission yields

Res params.

FF decay

How ? 11/09/2007 - FINUSTAR 2 6/20

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TALYS-1.2

• Released December 21, 2009, see www.talys.eu• Use of TALYS still increasing

- Estimated 400-500 users- About 160-200 publications using TALYS

• Some recent additions (present in TALYS-1.2):- Better fission + level density model from Bruyeres-le-Chatel- The option to easily/safely store the best input parameter set

per nucleus (“best y”)- More flexibility for covariance development and adjustment to

experimental data• TALYS can be used for

- In-depth nuclide/reaction evaluations (Recent examples from NRG: Na, Ca, Sc ,Fe ,Ge ,Pb ,Bi)

- Global multi-nuclide calculations- We are now merging these two

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The total TALYS code system

• TALYS: Nuclear model code, Fortran, 70000 lines (open source)

• TEFAL: ENDF-6/EAF formatting code, Fortran, 15000 lines

• TASMAN: Optimization and covariance program for TALYS, Fortran 10000 lines

• TARES: Resonance data and covariance generator, C++ 10000 lines

• TAFIS: code for data and covariance of average number of fission neutrons, C++ and Fortran, 3000 lines

• TANES: code for fission neutron spectra and covariances, C++ and Fortran, 3000 lines (includes RIPL code)

• AUTOTALYS: script to use the above codes and to produce nuclear data libraries in a systematic manner

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ResonanceParameters

.TARES

Experimental data

(EXFOR)

Nucl. model parameters TALYS

TEFAL

Output

Output

ENDFGen. purpose

file

ENDF/EAFActiv. file

NJOY

PROC.CODE

MCNP

FIS-PACT

Nuclear data scheme + covariances

-K-eff

-Neutron flux

-Etc.

-activation

- transmutation

Determ.code

Othercodes

+Uncertainties

+Uncertainties

+Covariances

+Covariances +Covariances

+(Co)variances

+Covariances

+Covariances

TASMAN

Monte Carlo: 1000 TALYS runs

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ResonanceParameters

.TARES

Experimental data

(EXFOR)

Nucl. model parameters TALYS

TEFAL

Output

Output

ENDFGen. purpose

file

ENDF/EAFActiv. file

NJOY

PROC.CODE

MCNP

FIS-PACT

Nuclear data scheme: Total Monte Carlo

-K-eff

-Neutron flux

-Etc.

- activation

- transmutation

Determ.code

Othercodes

+Uncertainties

+Uncertainties

+Covariances

+Covariances

TASMAN Monte Carlo: 1000 runs of all codes

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TENDL: Complete ENDF-6 data libraries

MF1: description and average fission quantitiesMF2: resonance dataMF3: cross sectionsMF4: angular distributionsMF5: energy spectraMF6: double-differential spectra, particle yields and residual productsMF8-10: isomeric cross sections and ratiosMF12-15: gamma yields, spectra and angular distributionsMF31: covariances of average fission quantities (TENDL-2010)MF32: covariances of resonance parametersMF33: covariances of cross sectionsMF34: covariances of angular distributionsMF35: covariances of fission neutron spectra (TENDL-2010) and

particle spectra (TENDL-2011)MF40: covariances of isomeric data (TENDL-2011)

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Some examples: differential data

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Oktavian for Co

Rochman and Koning, to appear in Fusion Engineering and Design

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Contents of TENDL-2009

• Neutron, proton, deuteron, triton, Helium-3, alpha and gamma libraries: transport (ENDF-6) and activation (EAF)

• 2400 nuclides (all with lifetime > 1 sec.)• 1170 nuclides (lifetime > 1000 sec) < 200 MeV, the rest < 60 MeV• Neutron library: 1170 nuclides (lifetime > 1000 sec) with complete

covariance data (MF31-MF35)• For all nuclides processed MCNP-libraries (n,p and d) and

processed multi-group covariances (neutrons only)Strategy:• Always keep completeness, global improvement in 2010, 2011,… • Extra effort for important nuclides, especially when high precision

is required (e.g. actinides): TALYS input file + uncertainties, resonance parameters + uncertainties, “unphysical actions”

• All libraries are always reproducible from scratch• All libraries based on compact reaction info• The ENDF-6/EAF libraries are created, not touched

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ResonanceParameters

.TARES

Experimental data

(EXFOR)

Nucl. model parameters TALYS

TEFAL

Output

Output

ENDFGen. purpose

file

ENDF/EAFActiv. file

NJOY

PROC.CODE

MCNP

FIS-PACT

Current system: Data for all isotopes

-K-eff

-Neutron flux

-Etc.

- activation

- transmutation

Determ.code

Othercodes

+Uncertainties

+Uncertainties

+Covariances

+Covariances

TASMAN Monte Carlo: 1000 runs of all codesBasic data

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Quality of data library =

Completeness (all reactions) (MF1-MF35, all MT-numbers)

Robust underlying physics (TALYS + improvements)

Reproduce diff. measurements (TALYS+EXFOR; EXFOR only)

Includes complete uncertainties (small for known reactions, large for unknown)Small uncertainties (for important and well-measured nuclides)

Correctness and processability (perfect format, flawless NJOY-processing)

Reproduce integ. measurements (responses, k-eff, etc.)

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Quality of proton nuclear data (A. Konobeyev, ND-2010)

ENDF/B-VII-p (LA-150): 30 nuclides TENDL-2009: 1170 nuclides

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TENDL for FENDL: possibilities

Fill gaps:• Proton libraries: Complete, versus 30 nuclides in ENDF/B-

VII (JENDL/HE?)• Deuteron libraries: is the only one existing (?), but requires

development of MCNPX• Neutron libraries

- Take nuclides which do not exist elsewhere- Complete covariance data: adopt?- Extends up to 200 MeV: adopt?- Complete gamma production data: adopt?

Or even:• Take TENDL when better than existing libraries

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FENDL for TENDL

• Feedback on the performance of TENDL, good or bad.

• We may normalize TENDL to FENDL for nuclide-reaction combinations where TALYS can not beat FENDL. After that, TENDL provides completeness with MF1-MF35.

• Progress on processing and validation issues for protons and deuterons (NJOY + MCNPX + FISPACT issues)

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Conclusions

We are approaching the situation in which the production of a complete ENDF-6 file is standard, quality assured and reproducible.

When this is indeed accomplished, the main challenges are:• Better physics models and parameterization of the nuclear models• Selecting and measuring good experimental dataNext, computer power does the rest

NRG offers TENDL to FENDL• To fill gaps in the fusion material chart• To adopt covariance data, for transport and activation libraries• To adopt high-energy data• To adopt complete proton and deuteron libraries• To adopt entire or parts of neutron libraries whenever the FENDL group

thinks that is appropriate

and only requests feedback in return.