Analysis of core physics experiments on irradiated BWR MOX fuel in the REBUS program

References

• 1999 . Full Core Loading of Mixed Oxide Fuels in Advanced Boiling Water Reactors , Nuclear Safety Commission of Japan . [in Japanese]
   Google Scholar
• Lance , B. , Marloye , D. Moerenhout , J. 2003 . Critical experiments: Recent and future international progammes in VENUS . Proceedings of the International Conference on Nuclear Critical Safety, ICNC2003 . October 20–24 2003 .
   Google Scholar
• Alander , A. , Misu , S. Thareau , S. 2008 . AREVA NP burnup credit investigation on irradiated MOX fuel within the REBUS BWR programme . Proceedings of the International Conference on PHYSOR 2008 . September 14–19 2008 .
   Google Scholar
• Yamamoto , T. , Ando , Y. and Hayashi , Y. 2008 . Analysis of core physics experiments on irradiated BWR MOX fuel in REBUS program . Proceedings of the International Conference on PHYSOR 2008 . September 14–19 2008 .
   Google Scholar
• 2009 . Experimental Results of REBUS Program and Their Theoretical Analysis , JNES-SS-0904, Japan Nuclear Energy Safety Organization . [in Japanese]
   Google Scholar
• Yamamoto , T. , Kawashima , K. Ando , Y. 2009 . Analysis of core physics experiments on fresh and irradiated BR3 MOX fuel in REBUS program . J. Nucl. Sci. Technol , 46 : 484
   Web of Science ®Google Scholar
• Okumura , K. , Kugo , T. Kaneko , K. 2007 . SRAC2006: A Comprehensive Neutronic Calculation Code system , JAERI-Data/Code 2007-004, Japan Atomic Energy Institute .
   Google Scholar
• Nakagawa , T. , Shibata , K. Chiba , S. 1995 . Japanese evaluated nuclear data library version 3 revision-2 . J. Nucl. Sci. Technol , 32 : 1259
   Web of Science ®Google Scholar
• Ishiguro , Y. PEACO-II: A Code for Calculation of Effective Cross Section in Heterogeneous System , 1974 JAERI-M-5527, Japan Atomic Energy Institute .
   Google Scholar
• Ando , Y. and Takano , H. 1999 . Estimation of LWR Spent Fuel Composition , JAERI-Research 99-004, Japan Atomic Energy Institute . [in Japanese]
   Google Scholar
• Tasaka , K. , Katakura , J. Ihara , H. 1990 . JNDC Nuclear Data Library of Fission Products – Second Version , JAERI-1320, Japan Atomic Energy Institute .
   Google Scholar
• 2005 . Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method) , ASTM E321-96 (Reapproved 2005), ASTM-International .
   Google Scholar
• Ando , Y. , Yamamoto , T. and Sugo , Y. 2011 . Analysis of measured isotopic compositions of high-burnup BWR MOX fuel . J. Nucl. Sci. Technol , 48 : 384
   Web of Science ®Google Scholar
• Okumura , K. , Mori , T. Nakagawa , M. 2000 . Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment . J. Nucl. Sci. Technol , 37 : 128
   Web of Science ®Google Scholar
• Nagaya , Y. , Okumura , K. Mori , T. 2005 . MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods , JAERI-1348, Japan Atomic Energy Institute .
   Google Scholar
• Yamamoto , T. , Ando , Y. Hayashi , Y. 2011 . Analysis of core physics experiments on fresh and irradiated PWR UO2 fuels in the REBUS program . J. Nucl. Sci. Technol , 48 : 1025
   Web of Science ®Google Scholar
• Shibata , K. , Kawano , T. Nakagawa , T. 2002 . Japanese Evaluated Nuclear Data Library Version 3 revision-3: JENDL-3.3 . J. Nucl. Sci. Technol , 39 : 1125
   Web of Science ®Google Scholar
• Fowler , T.B. , Vondy , D.R. and Cummingham , G.W. 1969 . Nuclear reactor analysis code: CITATION , ORNL-TM-2496, Oakridge National Laboratory .
   Google Scholar
• Alcouffe , R.E. 1995 . DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System , LA-12969-M, Los Alamos National Laboratory .
   Google Scholar
• Kanda , K. , Yamamoto , T. Matsuura , H. 1998 . MOX fuel core physics experiments and analysis – aiming for Plutonium effective use . Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn.) , 40 : 834 [in Japanese]
   Web of Science ®Google Scholar
• Roque , B. , Thiollay , N. Marimbeau , P. 2002 . Experimental validation of the code system “DARWIN” for spent fuel isotopic predictions in fuel cycle applications . Proceedings of the International Conference on the PHYSOR 2002 . October 7–10 2002 .
   Google Scholar