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ORIGINAL PAPER

Fission Gas Release in Irradiated UO2 Fuel at Burnup of 45 GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition

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Pages 966-972 | Received 25 May 2004, Accepted 13 Aug 2004, Published online: 15 Feb 2012

References

  • Fuketa , T. , Nakamura , T. and Ishijima , K. 1997 . “The status of the RIA test program in the NSRR,” . In Proc. 25th Water Reactor Safety Information Meeting (WRSM) Bethesda, Maryland, October 20–22 , NUREG/CP-0162 Vol. 2 , 1998 U. S. Nuclear egulatory Commission .
  • Papin , J. and Schmidt , F. 1997 . “The status of the CABRI-REP-Na test programme: Present understanding and still pending questions,” . In Proc. 25th Water Reactor Safety Information Meeting (WRSM) Bethesda, Maryland, October 20–22 , NUREG/CP-0162 Vol. 2 , 1998 U. S. Nuclear Regulatory Commission .
  • Nakamura , T. , Yoshinaga , M. Takahashi , M. 2000 . “Boiling water reactor fuel behavior under reactivity-initiated-accident conditions at burnup of 41 to 45GWd/tonne U,” . Nucl. Technol. , 129 : 141
  • Hayashi , Y. , Koyama , T. Koizumi , S. 1991 . “BWR fuel performance and recent R&D activities in Japan,” . In Proc. Int. Topical Mtg. LWR Fuel Performance Avignon, France, April 21–24 Vol. 1 , 36 American Nuclear Society . 1991
  • Suyama , K. , Iwasaki , T. and Hirakawa , N. 1997 . Integrated Burnup Calculation Code System SWAT JAERI-Data/Code 97–047, Japan Atomic Energy Research Institute (JAERI)
  • Tsuchihashi , T. , Ishiguro , Y. Kaneko , K. 1986 . Revised SRAC Code System JAERI 1302 Japan Atomic Energy Research Institute (JAERI)
  • Okumura , K. , Kaneko , K. and Tsuchihashi , K. 1996 . SRAC95; General Purpose Neutronics Code System JAERI-Data/Code 96–015, Japan Atomic Energy Research Institute (JAERI)
  • Nakamura , T. , Takahashi , M. and Yoshinaga , M. 2000 . Evaluation of Burnup Characteristics and Energy Deposition during NSRR Pulse Irradiation Tests on Irradiated BWR Fuels JAERI-Re-search 2000–048, Japan Atomic Energy Research Institute (JAERI) [in Japanese]
  • Nakamura , T. , Yoshinaga , M. Sobajima , M. 1994 . “Boiling water reactor fuel behavior at burnup of 26 GWd/tonneU under reactivity initiated accident conditions,” . Nucl. Technol. , 108 : 45
  • Nakamura , T. , Yoshinaga , M. Sobajima , M. 1991 . 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 (JAERI)
  • Nakamura , T. , Yoshinaga , M. Ishijima , K. 1995 . 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 (JAERI)
  • Kusagaya , K. , Nakamura , T. Yoshinaga , M. Behavior of Irradiated BWR Fuel Under Simulated RIA Condition, Results of Tests FK-1 and 2 To be published in JAERI-Research, [in Japanese].
  • Ishimoto , S. , Hirai , M. , Ito , K. and Korei , Y. 1994 . “Effects of soluble fission products on thermal conductivities of nuclear fuel pellets,” . J. Nucl. Sci. Technol. , 31 : 796
  • Amaya , M. , Hirai , M. Sakurai , H. 2002 . “Thermal conductivities of irradiated UO2 and (U,Gd)O2 pellets,” . J. Nucl. Mater. , 300 : 57
  • Nuclear Power Engineering Corporation . The Annual Report on Irradiated Tests of High Burnup Fuels in FY 2001, Integrated Evaluation on Irradiation Behavior of BWR High Burnup Fuel , March 2002 [in Japanese]
  • Ohara , H. , Nomata , T. Irube , M. 1994 . “Fuel behavior during power ramp tests,” . In Proc. Int. Topical Mtg. LWR Fuel Performance, West Palm Beach, April 17–21 674 American Nuclear Society . 1991
  • Nakamura , T. , Yoshinaga , M. Takahashi , M. 2000 . “Boiling water reactor fuel behavior under reactivity-initiated-accident conditions at burnup of 41 to 45 GWd/tonneU,” . Nucl. Technol. , 129 : 141
  • Cunningham , M. E. , Freshley , M. D. and Lanning , D. D. 1992 . “Development and characteristics of the rim region in high burnup UO2 fuel pellets,” . J. Nucl. Mater. , 188 : 19
  • Nakamura , T. , Kusagaya , K. Fuketa , T. 2002 . “High burnup BWR fuel behavior under simulated reactivity-initiated-accident conditions,” . Nucl. Technol. , 138 : 246
  • Une , K. and Kashibe , S. 1992 . J. Nucl. Mater. , 189 : 210
  • Kashibe , S. and Une , K. 2000 . J. Nucl. Sci. Technol. , 37 : 530

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