Complete activation data libraries for all incident particles, all energies and including covariance data

Transcription

1 Complete activation data libraries for all incident particles, all energies and including covariance data Arjan Koning NRG Petten, The Netherlands Workshop on Activation Data EAF 2011 June , Prague, Czech Republic

2 Contents Introduction State of the TALYS empire Some new developments in data evaluation Difference between transport and activation files disappearing? Automatic optimization TENDL for neutrons TENDL for charged particles Conclusions 2

3 TALYS Nuclear model code by NRG Petten and CEA Bruyeres-le-Chatel Reactions: g,n,p,d,t,h,a induced reactions from 10-5 ev up to 250 MeV Release: Latest official version, TALYS-1.2, released december 21, Estimated users, > 300 publications Software issues: TALYS is ready to be used by persons other than the authors Very flexible: 4-line idiot-proof input (element, mass, projectile, energy), but also... > 250 keywords to change models, parameters, level of output, etc. 300 page manual, 20 widely varying sample cases Readable modular programming (extensions by others is relatively easy) Very robust, thanks to dripline-to-dripline and random input testing 3

4 TALYS code scheme 4

5 TALYS physics General use: TALYS can be used for - In-depth single nuclide/reaction analyses - Global multi-nuclide calculations Complete output: Total, partial (e.g. (n,n ) per discrete level, or (n,2np) and residual production cross sections, (Double)-differential spectra Angular distributions per discrete level Fission yields, Recoils, Isomeric production Astrophysical reaction rates Gamma production, etc, Recent accomplishment: option to use all optical, level density, fission and pre-equilibrium models phenomenologically (Woods-Saxon, Fermi gas, Hill-Wheeler, exciton) or microscopically (Hartree-Fock-Bogolyubov-based, by Hilaire, Goriely, Bauge) 5

6 Other people using TALYS (publications) publications Astrophysics; 56 General; 9 Nuclear models; 31 Medical; 32 High energy models and exps.; 70 Fusion; 22 Data libs and low energy exps.; 86 6

7 The total TALYS code system TALYS: Nuclear model code, Fortran, 70,000 lines (open source, NRG + CEA-DAM) TEFAL: ENDF-6/EAF formatting code, Fortran, 15,000 lines (AK) TASMAN: Optimization and covariance program for TALYS, Fortran 10,000 lines (AK) TARES: Resonance data and covariance generator, C++ 10,000 lines (DR) TAFIS: code for data and covariance of average number of fission neutrons, C++ and Fortran, 3,000 lines (DR) TANES: code for fission neutron spectra and covariances, C++ and Fortran, 3,000 lines (includes RIPL code) (DR) AUTOTALYS: script to use the above codes and to produce nuclear data libraries in a systematic manner (AK) This is all needed to bring nuclear data to technology 7

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9 Nuclear data scheme + covariances +Uncertainties Resonance Parameters. TARES +Covariances +Covariances Determ. code Output ENDF Gen. purpose file NJOY MCNP -K-eff -Neutron flux -Etc. Experimental data (EXFOR) TEFAL +Covariances Output ENDF/EAF Activ. file PROC. CODE FIS- PACT -activation - transmutation Nucl. model parameters TALYS +Covariances +(Co)variances +Covariances Other codes +Uncertainties Monte Carlo: 1000 TALYS runs TASMAN 9

10 Nuclear data scheme: Total Monte Carlo +Uncertainties Resonance Parameters. TARES Determ. code Output ENDF Gen. purpose file NJOY MCNP -K-eff -Neutron flux -Etc. Experimental data (EXFOR) TEFAL +Covariances Output ENDF/EAF Activ. file PROC. CODE FIS- PACT - activation - transmutation Nucl. model parameters TALYS Other codes +Covariances +Uncertainties TASMAN Monte Carlo: 1000 runs of all codes 10

11 Why transport and activation files? Legacy of old codes (MCNP, ORIGEN, etc.) which handle either transport or depletion using different types of data (libraries) Handling of reaction (transport + activation), fission yields and decay data often safely hidden to prevent flexible use [\cynical mode off] New software : Serpent (leppanen, VTT) Monte Carlo transport + depletion code Use of cross section, FY and RDD data close to trivial ACE files for transport and depletion part Flexibility makes it perfect for TENDL and/or Total Monte Carlo 11

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15 Automatic optimization: NRG s current evaluation method Analyze isotope in depth with TALYS (parameter fitting) and adopt resonance parameters Assign realistic uncertainties to all data Create > 1000 random data libraries inside these uncertainties Benchmark them all against all integral experiments containing the isotope Take the best random library and promote that one to the best file (including covariance data) Example: Cu-63,65 40 ICSBEP benchmarks Oktavian (larger weight) 15

16 Random libraries vs integral exps. 16

17 Best Cu-63,65 file vs crititcality exps 17

18 Best Cu63,65 file vs Oktavian 18

19 Best Cu-65 file: differential performance 19

20 TALYS Evaluated Nuclear Data Library: TENDL-2010 Neutron, proton, deuteron, triton, Helium-3, alpha and gamma libraries: transport (ENDF-6 format), activation, and x-y tables 2400 nuclides (all with lifetime > 1 sec.) 1170 nuclides (lifetime > 1000 sec) < 200 MeV, the rest < 60 MeV Neutron library: complete covariance data For all nuclides processed MCNP-libraries ( ACE-files ) (n,p and d) and processed multi-group covariances (neutrons only) Strategy: Always ensure completeness, global improvement in 2011, 2012, Production time: 2 months for 150 processors Extra effort for important nuclides, especially when high precision is required (e.g. actinides): Fitted model calculations and direct inclusion of experimental data. Keep the input files. All libraries are always reproducible from scratch All libraries based on compact reaction info: default TALYS input file or input file with adjusted parameters, parameter uncertainties, resonance parameters + uncertainties 20

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29 Quality of proton data (EXFOR vs MCNPX, A. Konobeyev, KIT) (Chi-2) (< C/E >) (H x F) ENDF/B-VII-p (LA-150): nuclides TENDL-2009: 1170 nuclides 29

30 Global predictive power 30

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32 Conclusions TALYS ( is - a user-friendly nuclear model code for reactions involving all light particles up to 200 MeV, - used, and validated, by a worldwide community, TENDL ( is - a complete nuclear data library for all incident particles in ENDF-6, EAF and human-readable (x-y) format - useful for activation codes and radiation transport codes like the current (photon, neutron, proton ACE files) and future (d,t,h,a ACE files) versions on MCNP(X) 32

33 Conclusions (Near-) Future: Medical isotope predictor based on TENDL nearing completion Format issues almost resolved - Number of ENDF-6 bugs decreasing - Only MF40 (cov. of isomers and res. prod.) remaining TENDL mass production now trivial: - Finally more emphasis on nuclide by nuclide optimization of central values and uncertainties - Simultaneous optimization of differential and integral performance for many nuclides, including JUKO Research input for 30 kev capture, RI, activation benchmarks etc. The only secret behind all this: discipline (QA) and reproducibility Next major stop - Manhattan