Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2017 (2017), Article ID 1264736, 16 pages
https://doi.org/10.1155/2017/1264736
Research Article

SUSD3D Computer Code as Part of the XSUN-2017 Windows Interface Environment for Deterministic Radiation Transport and Cross-Section Sensitivity-Uncertainty Analysis

Jožef Stefan Institute, Jamova 39, SI-1000 Ljubljana, Slovenia

Correspondence should be addressed to Ivan A. Kodeli

Received 9 February 2017; Accepted 3 July 2017; Published 17 October 2017

Academic Editor: Valerio Giusti

Copyright © 2017 Ivan A. Kodeli and Slavko Slavič. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. W. W. Engle Jr. and F. R. Mynatt, “ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering,” OECD/NEA Computer Code Collection, CCC-0254, http://www.oecd-nea.org/tools/abstract/detail/ccc-0254/, http://www.oecd-nea.org/tools/abstract/detail/ccc-0650/.
  2. W. A. Rhoades and D. B. Simpson, “DOORS, 1-, 2-, 3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport,” OECD/NEA Computer Code Collection, CCC-0650.
  3. R. E. Alcouffe et al., “DANTSYS3.0, 1-D, 2-D, 3-D MultiGroup Discrete Ordinate Method Transport, OECD/NEA Computer Code Collection, CCC-0547,” http://www.oecd-nea.org/tools/abstract/detail/ccc-0547/.
  4. R. E. Alcouffe, R. S. Baker, J. A. Dahl, S. A. Turner, and R. C. Ward, “PARTISN 5.97, 1-D, 2-D, 3-D time-dependent, multigroup deterministic parallel neutral particle transport code,” LA-UR-08-07258, NEA/Data Bank CCC-0760/01 Computer Code Collection, November 2008. View at Google Scholar
  5. I. Kodeli and S. Slavič, XSUN-2013, Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D, 2014, OECD NEA code package NEA-1882 (http://www.oecd-nea.org/tools/abstract/detail/nea-1882/) and RSICC code package CCC-825 (https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-825.html).
  6. S. Slavič and I. Kodeli, “Windows Interface Environment XSUN-2013 for OECD/NEA Transport and Sensitivity-Uncertainty Computer Codes TRANSX-2, PARTISN and SUSD3D,” in Proceedings of the 23rd International Conference Nuclear Energy for New Europe, Portorož, Slovenia, Sept. 8–11, 2014.
  7. 1997–2006, Copyright (c) Alaska Software.
  8. R. E. MacFarlane, “TRANSX 2.15, Code System to Produce Neutron, Photon, and Particle Transport Tables for Discrete-Ordinates and Diffusion Codes from Cross Sections in MATXS Format, RSICC Peripheral Shielding Routine Collection,” PSR-317, 1995. View at Google Scholar
  9. R. E. MacFarlane and D. W. Muir, “The NJOY nuclear data processing system,” Manual LA-12740-M, 1999. View at Google Scholar
  10. I. Kodeli, “Multidimensional deterministic nuclear data sensitivity and uncertainty code system: Method and application,” Nuclear Science and Engineering, vol. 138, no. 1, pp. 45–66, 2001. View at Publisher · View at Google Scholar · View at Scopus
  11. I. Kodeli, The SUSD3D Code for Cross-Section Sensitivity and Uncertainty Analysis – Recent Development, vol. 104, Transactions of the American Nuclear Society, Hollywood, Florida, June 26–30, 2011. View at Scopus
  12. FENDL-3.1, https://www-nds.iaea.org/fendl3/.
  13. M. B. Chadwick et al., “ENDF/B-VII.1: Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data,” Nuclear Data Sheets, vol. 112, 2887, 2011. View at Google Scholar
  14. K. Shibata et al., “JENDL-4.0: a new library for nuclear science and engineering,” Journal of Nuclear Science and Technology, vol. 48, no. 1, pp. 1–30, 2011. View at Publisher · View at Google Scholar · View at Scopus
  15. “ZZ-SCALE6.0/COVA-44G,44-group cross-section covariance library, USCD1236/03,” 2012, OECD/NEA DB Computer code collection.
  16. I. Kodeli, “ANGELO-LAMBDA, Covariance matrix interpolation and mathematical verification, NEA-DB Computer Code Collection,” 2008, NEA-1798/02.
  17. N. Soppera, MeshTal Viewer and Sensitivities Viewer, 1988, http://www.oecd-nea.org/webstart/.
  18. I. Kodeli, SUSD3D, 1-, 2-, 3-Dimensional Cross Section Sensitivity and Uncertainty Code, NEA-1628/03 OECD/NEA DB Computer code collection, 2008.
  19. L. N. Usachev, “A generalized perturbation method for bi-linear functionals of the real and adjoint neutron fluxes,” in Proceedings of the Int. Conf. on Peaceful Uses of Nuclear Energy, A. Gandini, Ed., vol. 21, pp. 755–765, 1967, Geneva (1955). View at Publisher · View at Google Scholar · View at Scopus
  20. W. A. Rhoades and F. R. Mynatt, “The DOT-III Two-Dimensional Discrete Ordinates Transport Code,” Tech. Rep. ORNL-TM-4280, Oak Ridge National Laboratory, 1973. View at Publisher · View at Google Scholar
  21. I. Kodeli, “On the Equivalence between the SAGEP Sensitivity Method and the ENDF-102 Formalism for the 'Correction' of Fission Spectra Covariance Matrix,” OECD/NEA, 2008. View at Google Scholar
  22. I. Kodeli, A. Trkov, R. Capote, Y. Nagaya, and V. Maslov, “Evaluation and use of the prompt fission neutron spectrum and spectra covariance matrices in criticality and shielding,” Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 610, no. 2, pp. 540–552, 2009. View at Publisher · View at Google Scholar · View at Scopus
  23. Y. Nagaya, I. Kodeli, G. Chiba, and M. Ishikawa, “Evaluation of sensitivity coefficients of effective multiplication factor with respect to prompt fission neutron spectrum,” Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 603, no. 3, pp. 485–490, 2009. View at Google Scholar
  24. “Scale: A comprehensive modeling and simulation suite for nuclear safety analysis and design,” 2011, ORNL/TM-2005/39, Version 6.1.
  25. M. Aufiero, A. Bidaud, M. Hursin et al., “A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT,” Annals of Nuclear Energy, vol. 85, pp. 245–258, 2015. View at Publisher · View at Google Scholar · View at Scopus
  26. MCNP6 Users Manual - Code Version 6.1.1beta, LA-CP-14-00745, 2014.
  27. I. Kodeli, On how Sensitive the Cross-Section Sensitivity Calculations are to PN Order Approximations, PHYSOR 2014, The Role of Reactor Physics Toward a Sustainable Future, Kyoto, Japan, Sept. 28 - Oct. 3, 2014.
  28. I. Kodeli, “Sensitivity and Uncertainty in the Effective Delayed Neutron Fraction βeff (Method & SNEAK-7A Example),” Proc. UAM-5 Workshop, Stockholm, 2011, NEA-1769/04 package, OECD/NEA Data Bank. View at Google Scholar
  29. I.-A. Kodeli, “Sensitivity and uncertainty in the effective delayed neutron fraction (βeff),” Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 715, pp. 70–78, 2013. View at Publisher · View at Google Scholar · View at Scopus
  30. I. Kodeli and W. Zwermann, “Evaluation of uncertainties in βeff by means of deterministic and monte carlo methods,” Nuclear Data Sheets, vol. 118, no. 1, pp. 370–373, 2014. View at Publisher · View at Google Scholar · View at Scopus
  31. International Handbook of Evaluated Criticality Safety Benchmark Experiments, 2015, available on DVD-ROM, NEA/NSC/DOC(95)03.
  32. “Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations,” in Proceedings of the International Evaluation Co-operation 26, NEA/WPEC-26, OECD/NEA, Paris, 2008.
  33. G. R. Keepin, Physics of Nuclear Kinetics, Addison-Wesley, Reading, Massachusetts, USA, 1965. View at Publisher · View at Google Scholar
  34. International Handbook of Evaluated Reactor Physics Benchmark Experiments, available on DVD-ROM, NEA/NSC/DOC(2006)1, 2015.
  35. I. Kodeli, K. Kondo, R. L. Perel, and U. Fischer, “Cross-section sensitivity and uncertainty analysis of the FNG copper benchmark experiment,” Fusion Engineering and Design, vol. 109–111, pp. 1222–1226, 2016. View at Publisher · View at Google Scholar · View at Scopus
  36. U. Fischer, P. Batistoni, A. Klix, I. Kodeli, D. Leichtle, and R. L. Perel, “Neutronics R & D efforts in support of the European breeder blanket development programme,” Nuclear Fusion, vol. 49, no. 6, Article ID 065009, 2009. View at Publisher · View at Google Scholar · View at Scopus
  37. I. A. Kodeli, V. Mastrangelo, E. Ivanov et al., “OECD/NEA intercomparison of deterministic and Monte Carlo cross-section sensitivity codes using SNEAK-7 benchmarks,” in Proceedings of the Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016, Sun Valley, Idaho, USA, May 2016. View at Scopus
  38. I. A. Kodeli, M. Aufiero, and W. Zwermann, “Comparison of deterministic and Monte Carlo codes SUSD3D, serpent and XSUSA for beta-effective sensitivity calculations,” in Proceedings of the Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016, Sun Valley, Idaho, USA, May 2016. View at Scopus
  39. P. Romojaro, F. Álvarez-Velarde, I. Kodeli et al., “Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations,” Annals of Nuclear Energy, vol. 101, pp. 330–338, 2017. View at Publisher · View at Google Scholar · View at Scopus
  40. K. Ivanov et al., Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs, Volume I: Specification and Support Data for the Neutronics Cases (Phase I), vol. 7, Version 2.1, NEA/NSC/DOC(2013), OECD Nuclear Energy Agency, 2013.
  41. V. Mastrangelo, I. Kodeli, and E. Sartori, “Proposal of a Benchmark for Stochastic and Deterministic Analyses of Nuclear Data Sensitivities and Uncertainties,” Proc. Workshop on Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis (UAM 2006), 2006, Pisa, 28/29 April 2006, Package NEA-1769: ZZ-UAM-LWR (30-JUN-2006), http://www.nea.fr/abs/html/nea-1769.html. View at Google Scholar
  42. E. Ivanov, “SNEAK 7A and 7B Pu-Fuelled Fast Critical Assemblies in the Karlsruhe Fast Critical Facility,” Internal Reviewers V. Mastrangelo, I. Kodeli, NEA/NSC/DOC(2006)1, LMFR, SNEAK-LMFR-EXP-001, CRIT-SPEC-COEF-KIN-RRATE-MISC (March 2008).
  43. P. Sabouri, Application of Perturbation Theory Methods to Nuclear Data Uncertainty Propagation using the Collision Probability Method [Ph.D. thesis], Université de Grenoble, France, 2013.
  44. I. Kodeli, “SUSD3D Cross-Section Sensitivity and Uncertainty Code as Part of the XSUN-2017 Windows Interface Environment for Deterministic Radiation Transport Calculations, Workshop presented at M&C 2017,” in Proceedings of International Conference on Mathematics Computational Methods Applied to Nuclear Science Engineering, April 16-20, Jeju, Korea, 2017.