Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Integral nuclear data validation using experimental spent nuclear fuel compositions

  • Gauld, Ian C. (Oak Ridge National Laboratory) ;
  • Williams, Mark L. (Oak Ridge National Laboratory) ;
  • Michel-Sendis, Franco (OECD Nuclear Energy Agency) ;
  • Martinez, Jesus S. (Oak Ridge National Laboratory)
  • Received : 2017.06.01
  • Accepted : 2017.07.05
  • Published : 2017.09.25
Download PDF
⟨ Previous Next ⟩

Abstract

Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. The database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.

Keywords

References

  1. M.B. Chadwick, M. Herman, P. Oblozinský, M.E. Dunn, Y. Danon, A.C. Kahler, D.L. Smith, B. Pritychenko, G. Arbanas, R. Arcilla, R. Brewer, D.A. Brown, R. Capote, A.D. Carlson, Y.S. Cho, H. Derrien, K. Guber, G.M. Hale, S. Hoblit, S. Holloway, T.D. Johnson, T. Kawano, B.C. Kiedrowski, H. Kim, S. Kunieda, N.M. Larson, L. Leal, J.P. Lestone, R.C. Little, E.A. McCutchan, R.E. MacFarlane, M. MacInnes, C.M. Mattoon, R.D. McKnight, S.F. Mughabghab, G.P.A. Nobre, G. Palmiotti, A. Palumbo, M.T. Pigni, V.G. Pronyaev, R.O. Sayer, A.A. Sonzogni, N.C. Summers, P. Talou, I.J. Thompson, A. Trkov, R.L. Vogt, S.C. van der Marck, A. Wallner, M.C. White, D. Wiarda, P.G. Young, ENDF/B-VII.1: nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112 (2011) 2887-2996. https://doi.org/10.1016/j.nds.2011.11.002
  2. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I-IX, Organization for Economic Co-operation and DevelopmenteNuclear Energy Agency (OECD-NEA), Paris, 2014. NEA No. 7166.
  3. International Handbook of Evaluated Reactor Physics Benchmark Experiments, NEA/NSC/DOC(2006)1, Organisation for Economic Co-operation and Development/Nuclear Energy Agency, 2014. NEA No. 7173.
  4. G. Palmiotti, J.B. Briggs, T. Kugo, E. Trumble, A.C. Kahler, D. Lancaster, Applications of integral benchmark data, Nucl. Sci. Eng. 178 (2014) 295-310. https://doi.org/10.13182/NSE14-33
  5. M. Mochizuki, K. Suyama, Y. NomurA, H. Okuno, Spent Fuel Composition Database System on WWW - SFCOMPO on WWW Ver. 2, JAERI-Data/Code 2001-020, Japan Atomic Energy Research Institute, 2001 [In Japanese].
  6. K. Suyama, M. Murazaki, K. Ohkubo, Y. Nakahara, G. Uchiyama, Re-evaluation of assay data of spent nuclear fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems, Ann. Nucl. Energy 38 (2011) 930-941. https://doi.org/10.1016/j.anucene.2011.01.025
  7. G. Ilas, I.C. Gauld, G. Radulescu, Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE, Ann. Nucl. Energy 46 (2012) 43-55. https://doi.org/10.1016/j.anucene.2012.03.012
  8. The JEF-2.2 Nuclear Data Library, NEA Data Bank, 2000. JEFF Report 17.
  9. Validation of the JEFF-3.1 Nuclear Data Library, NEA Data Bank, 2013. JEFF Report 23.
  10. A. Santamarina, D. Bernard, Re-estimation of nuclear data and covariances using integral experiments - application to JEFF3 Library, in: Proceedings of the International Conference on Mathematics & Computational Methods (M&C 2017), 2017. Jeju, Japan.
  11. SCALE Code System, ORNL/TM-2005/39, Version 6.2.1. Available from the Radiation Safety and Information Computational Center as Package CCC-834 SCALE 6.2.1, 2016.
  12. SFCOMPO 2.0 - Database of Measured Isotopic Concentrations of Spent Nuclear Fuel, with Operational Histories and Design Data [Internet]. [Accessed 2017 Aug 2]. Available from: http://www.oecd-nea.org/sfcompo/.
  13. WPNCS Expert Group on Assay Data of Spent Nuclear Fuel (ADSNF) [Internet]. [Accessed 2017 Aug 2]. Available from: https://www.oecd-nea.org/science/wpncs/ADSNF/index.html.
  14. Evaluation Guide for the Evaluated Spent Nuclear Fuel Assay Database (SFCOMPO), NEA/NSC/R(2015)8, Organization for Economic Co-operation and Development-Nuclear Energy Agency (OECD-NEA), Paris, 2016.
  15. I. Hill, N. Soppera, M. Bossant, IDAT: the international handbook of evaluated reactor physics benchmark experiments database and analysis tool, Nucl. Sci. Eng. 178 (2014) 280-294. https://doi.org/10.13182/NSE14-37
  16. J.B. Briggs, A.N. Ellis, Y. Rugama, N. Soppera, M. Bossant, Identification of integral benchmarks for nuclear data testing using DICE (database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments), J. Korean Phys. Soc. 59 (2011) 1115-1118. https://doi.org/10.3938/jkps.59.1115
  17. I. Fast, Y. Aksyutina, H. Tietze-Jaensch, D. Bosbach, Determination of bandwidths of PWR-$UO_2$ spent fuel radionuclide inventory based on real operational history data, IEEE Trans. Nucl. Sci. 63 (2016) 2331-2335. https://doi.org/10.1109/TNS.2016.2586142
  18. B.T. Rearden, TSUNAMI-3D: Control Module for Three-Dimensional Cross-Section Sensitivity and Uncertainty Analysis for Criticality, ORNL/TM-2005/39, Version 5, 2005.
  19. Assessment of Existing Nuclear Data Adjustment Methodologies, NEA/NSC/WPEC/DOC(2010)429, An Intermediate Report by the Working Party on International Evaluation Co-operating of the NEA Nuclear Science Committee, WPEC-33, Organization for Economic Co-operation and Development-Nuclear Energy Agency (OECD-NEA), Paris, 2011.
  20. A. Gandini, Time-Dependent Generalized Perturbation Methods for Burnup Analysis, CNEN RT/FI(75) 4, CNEBN, Rome, 1975.
  21. M.L. Williams, C.R. Weisbin, Sensitivity and Uncertainty Analysis for Functionals of the Time-Dependent Nuclide Density Field, Oak Ridge National Laboratory, 1978. ORNL-5393.
  22. M.L. Williams, Development of depletion perturbation theory for coupled neutron/nuclide fields, Nucl. Sci. Eng. 70 (1979) 20-36. https://doi.org/10.13182/NSE79-3
  23. A.E. Isotalo, W.A. Wieselquist, A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN,, Ann. Nucl. Energy 85 (2015) 68-77. https://doi.org/10.1016/j.anucene.2015.04.037

Cited by

  1. Data assimilation of post-irradiation examination data for fission yields from GEF vol.6, pp.None, 2020, https://doi.org/10.1051/epjn/2020015
  2. An Integral Experiment on Polyethylene Using Radiative Capture in Indium Foils in a High Flux D-D Neutron Generator vol.194, pp.10, 2017, https://doi.org/10.1080/00295639.2020.1769964
  3. SFCOMPO DATABASE OF SPENT NUCLEAR FUEL ASSAY DATA - THE NEXT FRONTIER vol.247, pp.None, 2017, https://doi.org/10.1051/epjconf/202124710019