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ORIGINAL PAPER

Radionuclide Release from Mixed-Oxide Fuel under High Temperature at Elevated Pressure and Influence on Source Terms

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Pages 451-461 | Received 04 Aug 2004, Accepted 01 Mar 2005, Published online: 15 Feb 2012

References

  • Nakamura , T. , Hidaka , A. Hashimoto , K. 1999 . Research Program (VEGA) on the Fission Product Release from Irradiated Fuel , Japan Atomic Energy Research Institute (JAERI) . JAERI-Tech 99–036
  • Kudo , T. , Hidaka , A. Nakamura , T. 2001 . “Influence of pressure on cesium release from irradiated fuel at temperatures up to 2,773 K,” . J. Nucl. Sci. Technol. , 38 ( 10 ) : 910 – 911 .
  • Hidaka , A. , Kudo , T. Nakamura , T. 2002 . “Decrease of cesium release from irradiated fuel in helium atmosphere under elevated pressure of 1.0 MPa at temperature up to 2,773 K,” . J. Nucl. Sci. Technol. , 39 ( 7 ) : 759 – 770 .
  • Hickman , J. W. 1983 . PRA Procedures Guide. A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants , U. S. Nuclear Regulatory Commission (USNRC) . NUREG/CR-2300
  • Ikusawa , Y. , Kikuchi , K. Ozawa , T. 2003 . Post Irradiation Examination for the FUGEN High Burn-up MOX Fuel Assembly (1) Nondestructive Examination , Japan Nuclear Cycle Development Institute (JNC) . JNC TN8410 2003–005
  • Hayashida , R. , Hidaka , A. Nakamura , T. 2001 . Operation and Maintenance Manuals for VEGA Apparatus on Radionuclide Release from Irradiated Fuel , Japan Atomic Energy Research Institute (JAERI) . JAERI-Tech 2001–029, [in Japanese]
  • Hidaka , A. , Kudo , T. Nakamura , T. 1999 . Current Status of VEGA Program and a Preliminary Test with Cesium Iodide , Japan Atomic Energy Research Institute (JAERI) . JAERI-Research 99–066, [in Japanese]
  • Kanazawa , T. , Hidaka , A. Kudo , T. 2004 . Methods for Separation of Cs from Acid Solution Dissolving Radionuclides and Microanalysis of Solution with ICP-AES , Japan Atomic Energy Research Institute (JAERI) . JAERI-Tech 2004–050, [in Japanese]
  • Hidaka , A. , Kudo , T. Nakamura , T. 2002 . “Enhancement of cesium release from irradiated fuel at temperature above 2,800 K,” . J. Nucl. Sci. Technol. , 39 ( 3 ) : 273 – 275 .
  • Fisher , S. B. , White , R. J. Cook , P. M. A. 2002 . “Microstructure of irradiated SBR MOX fuel and its relationship to fission gas release,” . Nucl. Mater. , 306 : 153 – 172 .
  • Ozawa , T. , Ikusawa , Y. Abe , T. “Performance of ATR MOX fuel assemblies irradiated to 40GWd/t,” . Proc. 2004 Int. Mtg., on LWR Fuel Performance . Orlando , Florida .
  • Croff , A. G. 1983 . “ORIGEN2: A versatile computer code for calculating the nuclide composition and characteristics of nuclear materials,” . Nucl. Technol. , 62 ( 3 ) : 335 – 352 .
  • Tsuchiuchi , Y. , Ishijima , K. and Yamahara , T. 1998 . Post Irradiation Examination Data of High Burnup PWR Fuel Rod [Rod No.:B15 (Assembly No.:NO1G13)] , Japan Atomic Energy Research Institute (JAERI) . JAERI-Data/Code 98–002
  • Booth , A. H. 1957 . A Method of Calculating Fission Gas Diffusion from UO2 Fuel and its Application to the X-2-f Loop Test Chalk River Report CRDC-721
  • Lorenz , R. A. and Osborne , M. F. 1995 . A Summary of ORNL Fission Product Release Tests with Recommended Release Rates and Diffusion Coefficients , U. S. Nuclear Regulatory Commission (USNRC) . NUREG/CR-6261
  • Morita , K. and Fischer , E. A. 1998 . “Thermodynamic properties and equations of state for fast reactor safety analysis, Part I: Analytic equation-of-state model,” . Nucl. Eng. Des. , 183 : 177 – 191 .
  • Kajimoto , M. , Muramatsu , K. Watanabe , N. “Development of THALES-2, A computer code for coupled thermal-hydraulics and FP transport analyses for severe accident at LWRs and its application to analysis of FP revaporization phenomena,” . Proc. Int. Topical Mtg. on Safety of Thermal Reactors . Portland . pp. 584 – 592 .
  • Kuhlman , D. J. , Lehmicke , D. J. Meyer , R. O. 1985 . CORSOR User's Manual , U. S. Nuclear Regulatory Commission (USNRC) . NUREG/CR-4173
  • Hatakeyama , Y. , Sudou , K. and Kanazawa , H. 2004 . Development of Fission Gas Measurement Technique in the Irradiated Fuel Pellet , Japan Atomic Energy Research Institute (JAERI) . JAERI-Tech 2004–033, [in Japanese]
  • Hidaka , A. , Kudo , T. Ishigami , T. 2004 . “Proposal of simplified model of radionuclide release from fuel under severe accident conditions considering pressure effect,” . J. Nucl. Sci. Technol. , 41 ( 12 ) : 1192 – 1203 .
  • Nuclear Safety Commission in Japan . 2001 . Nuclear Safety Guideline [in Japanese]
  • Ishikawa , J. , Muramatsu , K. and Sakamoto , T. 2002 . “Systematic source term analyses for Level 3 PSA of a BWR with Mark-II Type containment with THALES-2 code,” . Proc. Int. Conf. on Nucl. Eng. , 22080
  • Clement , B. , Hanniet , N. Repetto , G. 2003 . “LWR severe accident simulation: Synthesis of the results and interpretation of the First Phebus FP experiment FPT0,” . Nucl. Eng. Des. , 226 : 5 – 82 .

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