References
- 1999 . On fully loading MOX fuel in the Advanced Light Water Reactors Nuclear Safety Commission of Japan . Jun. 28, 1999 [in Japanese]
- Suyama , K. , Iwasaki , T. and Hirakawa , N. 1994 . “Analysis of post irradiation experiments in PWR using new data libraries” . J. Nucl. Sci. Technol. , 31 ( 6 ) : 596
- 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 ( 2 ) : 128
- Murphy , B. D. and Primm , R. T. III . 2000 . “Prediction of spent MOX and LEU fuel composition and comparison with measurements” . In Proc. Int. Conf. on the PHYSOR 2000 Pittsburgh , , USA May 7–12, 2000
- Chabert , C. , Santamarina , A. and Bioux , P. 2000 . “Elaboration and experimental validation of the APOLLO2 depletion transport route for PWR Pu recycling” . In Proc. Int. Conf. on the PHYSOR 2000 Pittsburgh , , USA May 7–12, 2000
- Fujiwara , D. and Kosaka , S. 2002 . “Isotopic concentration and criticality analysis of BWR spent nuclear fuel using CASMO” . In Proc. Int. Conf. on the PHYSOR 2002 Seoul , , Korea Oct. 2–10, 2002
- Roque , B. , Thiollay , N. Marimbeau , P. 2002 . “Experimental validation of the code system “DARWIN” for spent fuel isotopic predictions in fuel cycle applications” . In Proc. Int. Conf. on the PHYSOR 2002 Seoul , , Korea Oct. 2–10, 2002
- Suyama , K. , Mochizuki , H. and Kiyosumi , T. 2002 . “Revised burnup code system SWAT: description and validation using postirradiation examination data” . Nucl. Technol. , 138 ( 2 ) : 97
- Courcelle , A. , Santamarina , A. and Mengelle , S. 2004 . “Improvement of isotopic ratios prediction through Takahama-3 chemical assay with the JEFF3.0 nuclear data library” . In Proc. Int. Conf. on the PHYSOR 2004 Chicago , , USA Apr. 25–29, 2004
- Yamamoto , T. and Kawashima , K. 2004 . “Verification of lattice analysis method through BWR UO2 PIE data analysis” . In Proc. Int. Conf. on the PHYSOR 2004 Chicago , , USA Apr. 25–29, 2004
- Ando , Y. , Yoshioka , K. Mitsuhashi , I. 2003 . “Development and verification of Monte Carlo burnup calculation system” . In Proc. Int. Conf. on the ICNC2003 Tokai , , Japan Oct. 20–24, 2003
- Yamamoto , T. and Kanayama , Y. 2007 . “Lattice physics analysis of exposures and isotope inventories of U, Pu and Nd of irradiated BWR 9_9–9 UO2 fuel assemblies” . J. Nucl. Sci. Technol. , 45 ( 6 ) : 547 – 566 .
- Misu , S. , Spieling , H. , Moon , H. and Koschel , A. 2000 . “Pin-by-pin gamma scan measurement on MOX and UO2 fuel assemblies and evaluation” . In Proc. Int. Conf. on the PHYSOR 2000 Pittsburgh, Pennsylvania , , USA May 7–12, 2000
- Yamamoto , T. and Yamamoto , M. 2008 . “Analysis of rod-by-rod FP inventory distributions in BWR 8_8 UO2 assemblies using lattice physics method” . J. Nucl. Sci. Technol. , 45 ( 1 ) : 1
- Nakahara , Y. , Suyama , K. Inagawa , J. 2002 . “Nuclide composition benchmark data set for verifying burnup codes on spent light water reactor fuel” . Nucl. Technol. , 137 : 111
- 2002 . Safety Experiments of High Burn-up Fuel (BWR High Burn-up Fuel, Comprehensive Evaluation) Nuclear Power Engineering Corporation, Mar. . 2002, [in Japanese]
- 1986 . Application for Establishment Permit of Modification of Unit 2 of Fukushima Power Station 2 Tokyo Electric Power Company . Sept. 29, 1986 [in Japanese]
- 2005 . Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method) , ASTM E321–96
- Okumura , K. , Kaneko , K. and Tsuchihashiz , K. 1996 . SRAC95: General Purpose Neutronics Code System , JAERI-Data/Code 96–015 (JAERI) [in Japanese]
- Nakagawa , T. , Shibata , K. Chiba , S. 1995 . “Japanese evaluated nuclear data library version 3 revision-2” . J. Nucl. Sci. Technol. , 32 : 1259
- Kanda , K. , Yamamoto , T. Matuura , H. 1998 . “MOX fuel core physics experiments and analysis—aiming for Plutonium effective use—” . Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn. , 40 ( 11 ) : 834 [in Japanese]
- Nakahara , Y. , Suyama , K. and Suzaki , T. 2000 . Technical Development on Burn-up Credit for Spent LWR Fuels , JAERI-Tech 2000–071 [in Japanese]
- Okumura , K. 2003 . “Analysis of post-irradiation test data of LWR high burnup UO2 fuel using JENDL, JEF and ENDF/B” . Nuclear Data News , 74 : 39 [in Japanese]
- Tasaka , K. , Katakura , J. Ihara , H. 1990 . JNDC Nuclear Data Library of Fission Products—Second Version— , JAERI-1320
- 2003 . On 9×9 Fuel of Boiling Water Reactor , GLR-001, Global nuclear fuel-Japan [in Japanese]