Calculation of Nuclear Characteristic Parameters and Drawing Subcriticality Judgment Graphs of Infinite Fuel Systems for Typical Nuclear Fuels

References

• (Compiled by) Nuclear Materials Regulation Division/Nuclear Safety Bureau/Science and Technology Agency . 1988 . Nuclear Criticality Safety Handbook , Nikkan-shobou . [in Japanese]; (Translated by) Y. Naito and H. Okuno, Nuclear Criticality Safety Handbook (English Translation), JAERI-Review 95–013, (1995)
   Google Scholar
• 1975 . ENDF/B Summary Documentation, , 2nd Edition BNL-NCS-17541 (ENDF- 201) (ENDF/B-IV)
   Google Scholar
• Petrie , L. M. and Cross , N. F. 1975 . KENOIV, An Improved Monte Carlo Criticality Program ORNL-4938
   Google Scholar
• Komuro , Y. and Katakura , J. “The preliminary edition of Nuclear Criticality Safety Handbook of Japan (3): Calculation of criticality condition,” . Proc. ICNS′87, Int. Semin. on Nuclear Criticality Safety . Oct. 19–23 1987 , Tokyo , Japan. pp. 145
   Google Scholar
• Working Group on Nuclear Criticality Safety Data . 1999 . Nuclear Criticality Safety Handbook, Version 2 JAERI 1340, [in Japanese]; (Translated by) H. Okuno, Y. Nomura and S. Ryufuku, Nuclear Criticality Safety Handbook, Version 2 (English Translation), JAERI-Review 2001–028, (2001)
   Google Scholar
• Ogino , T. and Naito , Y. 1989 . Nuclear Criticality of Fuel Assembly Having Infinite Multiplication Factor Less than Unity JAERI-M 89–039, [in Japanese]
   Google Scholar
• Naito , Y. , Koyama , T. and Komuro , Y. 1986 . Critical Enrichment and Critical Density of Infinite Systems for Nuclear Criticality Safety Evaluation JAERI-M86–026, [in Japanese]
   Google Scholar
• Nakamaru , S. , Sugawara , N. , Naito , Y. , Katakura , J. and Okuno , H. 1986 . SIMCRI: A Simple Computer Code for Calculating Nuclear Criticality Parameters JAERI-M 86–027
   Google Scholar
• Naito , Y. , Tsuruta , S. , Matsumura , T. and Ohuchi , T. 1981 . MGCL-Processor: A Computer Code System for Processing Multigroup Constants Library JAERI-M9396
   Google Scholar
• Komuro , Y. , Okuno , H. , Naito , Y. , Oda , H. , Nagai , M. , Okuda , Y. , Sakai , T. and Shiota , M. 1993 . Generation and Verification of the Multi-group Constants Library MGCL-J3 for Nuclear Criticality Calculation JAERI-M93–190
   Google Scholar
• Shibata , K. , Nakagawa , T. , Asami , T. , Fukahori , T. , Narita , T. , Chiba , S. , Mizumoto , M. , Hasegawa , A. , Kikuchi , Y. , Nakajima , Y. and Igarasi , S. 1990 . Japanese Evaluated Nuclear Data Library, Version-3, -JENDL-3- JAERI 1319
   Google Scholar
• Okuno , H. , Umeda , K. , Komuro , Y. and Naito , Y. 1993 . Criticality Parameters and Data for Various Nuclear Fuel Materials in Infinite Dimensions—Calculations with the Combination of MGCL-J3 and SIMCRI JAERI-M93–135, [in Japanese]
   Google Scholar
• Nakagawa , T. , Shibata , K. , Chiba , S. , Fukahori , T. , Nakajima , Y. , Kikuchi , Y. , Kawano , T. , Kanda , Y. , Ohsawa , T. , Matsunobu , H. , Kawai , M. , Zukeran , A. , Watanabe , T. , Igarasi , S. , Kosako , K. and Asami , T. 1995 . “Japanese Evaluated Nuclear Data Library, version 3, revision 2: JENDL 3.2,” . J. Nucl. Sci. Technol. , 32 : 1259
   Web of Science ®Google Scholar
• Okumura , K. , Kaneko , K. and Tsuchihashi , K. 1996 . SRAC95; General Purpose Neutronics Code System JAERI-Data/Code 96–015, [in Japanese]
   Google Scholar
• Suyama , K. and Takada , T. 1998 . POST—The Post Library Processor for Criticality Calculation Using SRAC95 JAERI-Data/Code 98–035, [in Japanese]
   Google Scholar
• Sakurai , S. and Tachimori , S. 1996 . “Density equation of aqueous solution containing plutonium (IV), uranium (VI) and nitric acid,” . J. Nucl. Sci. Technol. , 33 : 187
   Web of Science ®Google Scholar
• Okuno , H. , Murazaki , M. , Sakurai , S. and Takahashi , S. “Atomic number densities for the 2nd version of Nuclear Criticality Safety Handbook/Data Collection,” (in preparation)
   Google Scholar
• Komuro , Y. and Hirano , Y. 1987 . Nuclear Criticality Data for Uranium Mass and Sphere Volume of Homogeneous Water-Reflected and—Moderated ADU JAERI-M 87–184
   Google Scholar
• Okada , H. , Yoshioka , M. , Fujinaga , F. and Tachihara , T. “Criticality safety analysis of ammonium diuranate sintering tanks in a fuel reconversion process,” . Proc. Int. Conf. on the Physic of Reactors, PHYSOR 96 . Sept. 16–20 1996 , Mito , Japan. Vol. 4 , pp. L-137
   Google Scholar
• Takano , M. 1994 . OECD/NEA Burnup Credit Criticality Benchmark—Result of Phase-1A JAERI-M 94–003, NEA/NSC/DOC(93)22
   Google Scholar
• Mori , T. and Nakagawa , M. 1994 . MVP/GMVP: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods JAERI-Data/Code 94–007, [in Japanese]
   Google Scholar
• Suyama , K. , Komuro , Y. , Takada , T. , Kawasaki , H. and Ouchi , K. 1998 . MAIL3.1: A Computer Program Generating Cross Section Sets for SIMCRI, ANISN-JR, KENO IV, KENO V, MULTI-KE-NO, MULTI-KENO-2 and MULTI-KENO-3.0 JAERI-Data/Code 98–004
   Google Scholar
• Pruvost , N. L. and Paxton , H. C. 1996 . Nuclear Criticality Safety Guide LA-12808
   Google Scholar