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J. PAPIN and F. SCHMIDT, "The Status of the CABRIREP-Na Test Programme: Present Understanding and Still Pending Questions," Proc. 25th Water Reactor Safety Information Meeting (WRSM), Bethesda, Maryland, October 20-22, 1997, NUREG/CP-0162, Vol. 2 (1998).
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Boiling water reactor fuel behavior at burnup of 26 GWd/tonne U under reactivity-initiated accident conditions
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T. NAKAMURA, M. YOSHINAGA, M. SOBAJIMA, K. ISHIJIMA, and T. FUJISHIRO, "Boiling Water Reactor Fuel Behavior at Burnup of 26 GWd/tonne U Under Reactivity-Initiated Accident Conditions," Nucl. Technol., 108, 45 (1994).
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Experimental data report for test TS-1, reactivity initiated accident test in NSRR with pre-irradiated BWR fuel rod
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Japan Atomic Energy Research Institute
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T. NAKAMURA, M. YOSHINAGA, M. SOBAJIMA, T. FUJISHIRO, O. HORIKI, T. KIKUCHI, T. YAMAHARA, and Y. ICHIHASHI, "Experimental Data Report for Test TS-1, Reactivity Initiated Accident Test in NSRR with Pre-Irradiated BWR Fuel Rod," JAERI-M 91-217, Japan Atomic Energy Research Institute (1992).
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5
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10444284779
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Experimental data report for test TS-5, reactivity initiated test in NSRR with pre-irradiated BWR fuel rod
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Japan Atomic Energy Research Institute
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T. NAKAMURA, M. YOSHINAGA, K. ISHIJIMA, S. KOBAYASHI, T. YAMAHARA, T. SUKEGAWA, and T. ITO, "Experimental Data Report for Test TS-5, Reactivity Initiated Test in NSRR with Pre-Irradiated BWR Fuel Rod," JAERI-Research 95-080, Japan Atomic Energy Research Institute (1995).
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6
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0005909296
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BWR fuel performance and recent R&D activities in Japan
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Avignon, France, April 21-24, 1991, American Nuclear Society
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Y. HAYASHI, T. KOYAMA, S. KOIZUMI, T. YASUDA, and M. NOMURA, "BWR Fuel Performance and Recent R&D Activities in Japan," Int. Topl. Mtg. LWR Fuel Performance, Avignon, France, April 21-24, 1991, Vol. 1, p. 36, American Nuclear Society (1991).
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0030092424
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Fission gas induced deformation of LWR fuel rods under reactivity initiated accident conditions
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T. NAKAMURA, H. SASAJIMA, T. FUKETA, and K. ISHIJIMA, "Fission Gas Induced Deformation of LWR Fuel Rods Under Reactivity Initiated Accident Conditions," J. Nucl. Sci. Technol., 33, 12, 229 (1996).
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8
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0005944819
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Integrated burnup calculation code system SWAT
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Japan Atomic Energy Research Institute
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K. SUYAMA, T. IWASAKI, and N. HIRAKAWA, "Integrated Burnup Calculation Code System SWAT," JAERI-Data/Code 97-047, Japan Atomic Energy Research Institute (1997).
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9
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0006442862
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Revised SRAC code system
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Japan Atomic Energy Research Institute
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K. TSUCHIHASHI, Y. ISHIGURO, K. KANEKO, and M. IDO, "Revised SRAC Code System," JAERI 1302, Japan Atomic Energy Research Institute (1986).
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SRAC95; general purpose neutronics code system
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Japan Atomic Energy Research Institute
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K. OKUMURA, K. KANEKO, and K. TSUCHIHASHI, "SRAC95; General Purpose Neutronics Code System," JAERI-Data/Code 96-015, Japan Atomic Energy Research Institute (1996).
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0342282703
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Evaluation of burnup and energy deposition in NSRR irradiated BWR fuel tests
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(to be published) (in Japanese)
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T. NAKAMURA, M. TAKAHASHI, R. HOSOYAMADA, K.OKONOGI, and M. YOSHINAGA, "Evaluation of Burnup and Energy Deposition in NSRR Irradiated BWR Fuel Tests," JAERI-Research (to be published) (in Japanese).
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JAERI-Research
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Nakamura, T.1
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0343152207
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Behavior of irradiated BWR fuel under simulated RIA condition [results of tests FK-1 and 2]
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to be published
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K. KUSAGAYA, T. NAKAMURA, M. YOSHINAGA, M. TAKAHASHI, and K. OKONOGI, "Behavior of Irradiated BWR Fuel Under Simulated RIA Condition [Results of Tests FK-1 and 2]," JAERI-Research (to be published).
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JAERI-Research
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13
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0003736534
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FRAP-T6: A computer code for the transient analysis of oxide fuel rods
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EGG-2104, EG&G Idaho
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L. J. SIEFKEN, C. M. ALLISON, M. P. BOHN, and S. O. PECK, "FRAP-T6: A Computer Code for the Transient Analysis of Oxide Fuel Rods," NUREG/CR-2148, EGG-2104, EG&G Idaho (1981).
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T. TORIMARU, T. YASUDA, and M. NAKATSUKA, "Changes in Mechanical Properties of Irradiated Zircaloy-2 Fuel Cladding Due to Short Term Annealing," J. Nucl. Mater., 238, 169 (1996).
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0005984458
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Behavior of preirradiated fuels under simulated RIA conditions
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Portland, Oregon, July 21-25, 1991, American Nuclear Society
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K. ISHIJIMA, S. TANZAWA, T. FUKETA, and T. FUJISHIRO, "Behavior of Preirradiated Fuels Under Simulated RIA Conditions," Proc. Int. Topl. Mtg. Safety of Thermal Reactors, Portland, Oregon, July 21-25, 1991, p. 577, American Nuclear Society (1991).
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0030092424
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Transient elongation of a fresh fuel rod under reactivity initiated accident conditions
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K. ISHIJIMA and T. NAKAMURA, "Transient Elongation of a Fresh Fuel Rod Under Reactivity Initiated Accident Conditions," J. Nucl. Sci. Technol., 33, 3, 229 (1996).
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0343152206
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Japan Atomic Energy Research Institute, Personal Communication
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K. ISHIJIMA, Japan Atomic Energy Research Institute, Personal Communication (1999).
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Ishijima, K.1
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0040703677
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Behavior of irradiated PWR fuel under simulated RIA condition [results of NSRR test MH-3]
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Japan Atomic Energy Research Institute
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H. SASAJIMA, T. FUKETA, Y. MORI, K. ISHIJIMA, S. KOBAYASHI, T. YAMAHARA, T. SUKEGAWA, and T. ITO, "Behavior of Irradiated PWR Fuel Under Simulated RIA Condition [Results of NSRR Test MH-3]," JAERI-Research 95-087, Japan Atomic Energy Research Institute (1995).
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19
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0342282699
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FASTGRASS: A mechanistic model for prediction of Xe, I, Cs, Te, Ba and Sr release from nuclear fuel under normal and severe accident conditions: User's guide for maintenance, workstation and personal computer applications
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U.S. Nuclear Regulatory Commission
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J. REST et al., "FASTGRASS: A Mechanistic Model for Prediction of Xe, I, Cs, Te, Ba and Sr Release from Nuclear Fuel Under Normal and Severe Accident Conditions: User's Guide for Maintenance, Workstation and Personal Computer Applications," NUREG/CR-5840, U.S. Nuclear Regulatory Commission (1992).
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NUREG/CR-5840
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