Overview of the Burnup Credit Activities of the Organization for Economic Cooperation and Development/nuclear Energy Agency (Oecd/nea)

REFERENCES

• Elliott Whitesides, G. (Ed.) Standard Problem Exercise on Criticality Codes for Dissolving Fissile Oxides in Acids. A Report of the NEACRP Criticality Working Group Prepared by the Oak Ridge National Laboratory, NEA/NEACRP/L (1988) 306 (1990).
   Google Scholar
• Santamarina, A. and Smith, H. (CEA Cadarache). NEACRP Theoretical Benchmark Exercise on Criticality Codes for Dissolv-ing Fissile Oxides in Acids. Benchmark No. 20, NEA/NEACRP/L 320 (1989).
   Google Scholar
• Santamarina, A. and Smith, H. (CEA Cadarache). Analysis of the Results of the OECD/NEA Fuel Dissolver Benchmark No. 19 through Neutron Balance Evaluation of International Criticality Calculations. December 1990, NEA/NEACRP/L 325 (1990).
   Google Scholar
• Golinelli, C., Dan-aud, A. and Marsault, P. The Experimental Results from CRISTO Qualification of the Predicted Criticality of Fuel Storages. NEA/NEACRP/L 236 (1979).
   Google Scholar
• Ermumcu, G., Gonnord, J., Meunier, A. and Nimal, J.C. Criticality Analysis for Storage and Shipping of Nuclear Fuel Elements Outside of Reactors. NEA/NEACRP/L 237 (1979).
   Google Scholar
• Standard Problem Exercise on Criticality Codes for Spent LWR Fuel Transport Containers. CNSI Report No 71, May 1982, CSNI Working Group (Unrestricted in June 1990) NEA/NEACRP/L 326 (1990).
   Google Scholar
• Standard Problem Exercise on Criticality Codes for Large Arrays of Packages of Fissile Materials. CNSI Report No 78, August 1984, CSNI Working Group (Um-estricted in June 1990) NEA/NEACRP/L 327 (1990).
   Google Scholar
• Nomura, Y., Brady, M. C., Briggs, J. B. and Sartori, E. OECD/NEA Working Party on Nuclear Criticality Safety: Challenge of New Realities. In: Proc. 12th Int. Conf. on the Packaging and Transportation of Radioactive Materials, PATRAM'98, Vol. 2, pp. 833–838,10–15 May 1998, Paris, France (presentation by M. C. Brady).
   Google Scholar
• Brady, M. C., Takano, M., Dehart, M. D., Okuno, H., Noun, A. and Sartori, E. Findings of the OECD/NEA Study on Burnup Credit. Paper presented at Int. Conf. on the Physics of Reactors, PHYSOR'96, Mito, Japan, 17–19 Sept. 1996.
   Google Scholar
• Brady, M. C., Okuno, H., Dehart, M. D., Noun, A. and Sartori, E. International Studies on Burnup Credit Criticality Safety by an OECD/NEA Working Group. Paper presented at the Int. Conf. on the Physics of Nuclear Science & Technology, Long Island, NY, 5–8 Oct. 1998.
   Google Scholar
• Takano, M. OECD/NEA Burnup Credit Criticality Benchmark — Result of Phase-1A. JAERI-M 94–003, NEA/NSC/DOC(93)22, January 1994.
   Google Scholar
• Dehart, M. D., Brady, M. C. and Parks, C. V. OECD/NEA Burnup Credit Criticality Benchmark — Phase 1-B Results. ORNL/TM-6901, NEA/NSC/DOC(96)06 (June 1996).
   Google Scholar
• Takano, M. and Okuno, H. OECD/NEA Burnup Credit Criticality Benchmark — Result of Phase H-A. JAERI-Research 96–003, NEA/NSC/DOC(96)01, February 1996.
   Google Scholar
• Noun, A. Burnup Credit Criticality Benchmark: Analysis of Phase H-B Results of a Conceptual PWR Spent Fuel Transpor-tation Cask. May 1998, IP5N/98-05, NEA/NSC/DOC 1 (1998).
   Google Scholar
• Okuno, H., Naito, Y. and Ando, Y. OECD/NEA Burn-up Credit Criticality Benchmark PhaseCriticality Calculationsof BWR Spent Fuel Assemblies in Storage and Transport. September 2000, JAERI-Research 2000–0441, NEA/NSC/DOC12 (2000).
   Google Scholar
• Takano, M. and Brady, M. OECD/NEA Burnup-Credit Criticality Benchmark — Part 1. Simple PWR Spent Fuel Cell. JAERI-M 94–003, NEA/NSC/DOC(93)22, January 1992.
   Google Scholar
• Dehart, M. D. and Parks, C. V. Issues Related to Criticality Safety Analysis for Burnup Credit Applications. In: Proc. Int. Conf. on Nuclear Criticality Safety, 17–21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar
• Kurosawa, M., Naito, Y. and Kaneko, T. Isotopic Composition of Spent Fuels for Criticality Safety Evaluation and Isotopic Composition Database (SFCOMPO). In: Proc. Int. Conf. on Nuclear Criticality Safety, 17–21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar
• Naito, Y. Databook of the Isotopic Composition of Spent Fuel in Light Water Reactors. JAERI-M 94–034 (1994).
   Google Scholar
• Kurosawa, M., Naito, Y., Sakamoto, H. and Kaneko, T. The Isotopic Compositions Database System on Spent Fuels in LWRs (SFCOMPO). JAERI-Data/Code 97–036, February 1997.
   Google Scholar
• Mitake, S., Sato, O. and Yoshizawa, N. An Analysis of PWR Fuel Post Irradiation Examination Data for the Burnup Credit Study. In: Proc. Int. Conf. on Nuclear Criticality Safety. 17-21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar
• Santamarina, A., Albarede, P., Andrieu, P., Chavuin, J. P., Garcia, F., Gastaldi, B, Gulliford, J. and Roque, B. Experimental Validation of Burnup Credit Calculations by Reactivity Worth Measurements in the MINERVE Reactor. In: Proc. Int. Conf. on Nuclear Criticality Safety, 17–21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar
• Gulliford, N. T. The Experimental Validation of Calculational Methods and Data for Burnup Credit. In: Proc. Int. Conf. on Nuclear Criticality Safety, 17–21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar
• Anno, J., Fouillaud, P., Grivot, P. and Pouliot, G. Description and Exploitation of Benchmarks Involving 149Sm, A Fission Product Taking Part in the Burnup Credit in Spent Fuels. In: Proc. Int. Conf. on Nuclear Criticality Safety, 17–21 September 1995, Albuquerque, New Mexico (1995).
   Google Scholar