FISPACT-II: An Advanced Simulation System for Activation, Transmutation and Material Modelling

Abstract Fispact-II is a code system and library database for modelling activation-transmutation processes, depletion-burn-up, time dependent inventory and radiation damage source terms caused by nuclear reactions and decays. The Fispact-II code, written in object-style Fortran, follows the evolution of material irradiated by neutrons, alphas, gammas, protons, or deuterons, and provides a wide range of derived radiological output quantities to satisfy most needs for nuclear applications. It can be used with any ENDF-compliant group library data for nuclear reactions, particle-induced and spontaneous fission yields, and radioactive decay (including but not limited to TENDL-2015, ENDF/B-VII.1, JEFF-3.2, JENDL-4.0u, CENDL-3.1 processed into fine-group-structure files, GEFY-5.2 and UKDD-16), as well as resolved and unresolved resonance range probability tables for self-shielding corrections and updated radiological hazard indices. The code has many novel features including: extension of the energy range up to 1 GeV; additional neutron physics including self-shielding effects, temperature dependence, thin and thick target yields; pathway analysis; and sensitivity and uncertainty quantification and propagation using full covariance data. The latest ENDF libraries such as TENDL encompass thousands of target isotopes. Nuclear data libraries for Fispact-II are prepared from these using processing codes PREPRO, NJOY and CALENDF. These data include resonance parameters, cross sections with covariances, probability tables in the resonance ranges, PKA spectra, kerma, dpa, gas and radionuclide production and energy-dependent fission yields, supplemented with all 27 decay types. All such data for the five most important incident particles are provided in evaluated data tables. The Fispact-II simulation software is described in detail in this paper, together with the nuclear data libraries. The Fispact-II system also includes several utility programs for code-use optimisation, visualisation and production of secondary radiological quantities. Included in the paper are summaries of results from the suite of verification and validation reports available with the code.

[1]  Mark R. Gilbert,et al.  Inventory Simulations under Neutron Irradiation: Visualization Techniques as an Aid to Materials Design , 2014 .

[2]  M. Gilbert,et al.  PKA distributions: Contributions from transmutation products and from radioactive decay , 2016 .

[3]  Jean-Christophe Sublet,et al.  Energy spectra of primary knock-on atoms under neutron irradiation , 2015, 1506.08554.

[4]  N. Cho,et al.  Whole-Core Transport Solutions with 2-D/1-D Fusion Kernel via p-CMFD Acceleration and p-CMFD Embedding of Nonoverlapping Local/Global Iterations , 2015 .

[5]  T P Fell,et al.  Committed equivalent organ doses and committed effective doses from intakes of radionuclides , 1991 .

[6]  J. Hardy,et al.  The essential decay of pandemonium: A demonstration of errors in complex beta-decay schemes , 1977 .

[7]  J.-Ch. Sublet,et al.  Inventory Uncertainty Quantification using TENDL Covariance Data in Fispact-II , 2015 .

[8]  J. H. Hubbell,et al.  Tables of X-Ray Mass Attenuation Coefficients and Mass Energy-Absorption Coefficients 1 keV to 20 MeV for Elements Z = 1 to 92 and 48 Additional Substances of Dosimetric Interest , 1995 .

[9]  A Probability Table Based Cross Section Processing System: CALENDF - 2001 , 2002 .

[10]  M. Gilbert,et al.  Decay heat validation, FISPACT-II & TENDL-2013,-2012 and EAF-2010 nuclear data libraries , 2013 .

[11]  G. Rimpault,et al.  ERANOS 2.1 : International Code System for GEN IV Fast Reactor Analysis , 2006 .

[12]  J. H. Hubbell,et al.  Photon mass attenuation and mass energy-absorption coefficients for H, C, N, O, Ar, and seven mixtures from 0.1 keV to 20 MeV. , 1977, Radiation research.

[13]  Gregory Gutin,et al.  Digraphs - theory, algorithms and applications , 2002 .

[14]  T. Hutton,et al.  Optimising differential data formats for Monte-Carlo radiation transport in the fusion regime , 2016 .

[15]  K.-H. Schmidt,et al.  General Description of Fission Observables: GEF Model Code , 2016 .

[16]  F. Käppeler,et al.  NEUTRON CROSS SECTIONS FOR NUCLEOSYNTHESIS STUDIES , 2000 .

[17]  I. Dillmann,et al.  KADoNiS v0.3 - the third update of the Karlsruhe Astrophysical Database of Nucleosynthesis in Stars , 2009 .

[18]  R. A. Forrest,et al.  The European Activation File, EAF-2005 , 2005 .

[19]  Said F. Mughabghab,et al.  Atlas of Neutron Resonances: Resonance Parameters and Thermal Cross Sections. Z=1-100 , 2006 .

[20]  R. A. Forrest.  The European Activation File: EAF-2005 biological, clearance and transport libraries , 2005 .

[21]  G. I. Bell,et al.  Nuclear Reactor Theory , 1952 .

[22]  M. Gilbert,et al.  Decay heat validation, FISPACT-II & TENDL-2013, JEFF-3.2, ENDF/B-VII.1 and JENDL-4.0 nuclear data libraries , 2014 .

[23]  I. Goncalves,et al.  Universal curve of epithermal neutron resonance self-shielding factors in foils, wires and spheres , 2003 .

[24]  Jean-Christophe Sublet,et al.  ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments , 2011 .

[25]  Wayne Arter,et al.  Sensitivity Analysis for Activation Problems , 2014, ICS 2014.

[26]  R. Grimes,et al.  The Impact of Neutron Cross Section Group Structures on the Accuracy of Radiological Source Models , 2015 .

[27]  R. Smither,et al.  SPECTER: neutron damage calculations for materials irradiations , 1985 .

[28]  J. H. Hubbell,et al.  Photon mass attenuation and energy-absorption coefficients , 1982 .

[29]  M. Gilbert,et al.  Scoping of material response under DEMO neutron irradiation: comparison with fission and influence of nuclear library selection , 2016, 1604.08496.

[30]  I. Goncalves,et al.  Universal curve of the thermal neutron self-shielding factor in foils, wires, spheres and cylinders , 2004 .

[31]  A. M. Dunker,et al.  Efficient calculation of sensitivity coefficients for complex atmospheric models , 1981 .

[32]  N. P. Baumann.  RESONANCE INTEGRALS AND SELF-SHIELDING FACTORS FOR DETECTOR FOILS , 1963 .

[33]  V. Gopalakrishnan,et al.  Self-shielding and energy dependence of dilution cross-section in the resolved resonance region , 1998 .

[34]  R. A. Forrest.  Importance diagrams—a novel presentation of the response of a material to neutron irradiation , 1998 .

[35]  Richard B. Firestone,et al.  Table of Radioactive Isotopes , 1986 .

[36]  Alan C. Hindmarsh,et al.  Description and use of LSODE, the Livermore Solver for Ordinary Differential Equations , 1993 .

[37]  J.-C. Sublet.  JEFF-3.1, ENDF/B-VII and JENDL-3.3 Critical Assemblies Benchmarking With the Monte Carlo Code TRIPOLI , 2008, IEEE Transactions on Nuclear Science.

[38]  Optimization Algorithms for Multigroup Energy Structures , 2016 .

[39]  L. W. Packer.  The European Activation File: EAF-2010 biological, clearance and transport libraries , 2010 .

[40]  R. A. Forrest,et al.  FISPACT-2007: User manual , 2007 .

[41]  R. A. Forrest.  The European Activation File: EAF-2005 decay data library , 2005 .

[42]  Arjan J. Koning,et al.  Modern Nuclear Data Evaluation with the TALYS Code System , 2012 .

[43]  I. Goncalves,et al.  The calculation of neutron self-shielding factors of a group of isolated resonances , 2004 .

[44]  S. Kailas,et al.  RIPL – Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations , 2009 .

[45]  B. Pritychenko,et al.  Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC) , 2014, 2002.07114.

[46]  Mohamed ElBaradei.  Regulations for the Safe Transport of Radioactive Material , 2009 .

[47]  R. A. Forrest,et al.  Comprehensive handbook of activation data calculated using EASY-2003 , 2006 .

[48]  R. A. Forrest,et al.  The JEFF-3.0/A Neutron Activation File - EAF-2003 into ENDF-6 format - Summary Documentation , 2004 .

[50]  Robert E. MacFarlane,et al.  Methods for Processing ENDF/B-VII with NJOY , 2010 .

[51]  R. A. Forrest,et al.  EASY-97: a multipurpose activation and transmutation code system , 1997, 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).

[52]  藤夫 前川,et al.  Compilation of benchmark results for fusion related nuclear data , 1998 .

[53]  N. Higham,et al.  Ranking the Importance of Nuclear Reactions for Activation and Transmutation Events , 2015, 1502.07137.

[54]  Arjan J. Koning,et al.  From average parameters to statistical resolved resonances , 2013 .