References
- Hickman , J. W. 1983 . PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants NUREG/CR-2300
- Rogovin , M. 1979 . Three Mile Island: A Report to the Commissioners and to the Public Vol. 1 , NUREG/CR-1250
- Osborne , M. F. and Lorenz , R. A. 1992 . “ORNL studies of fission product release under LWR severe accident conditions,” . Nucl. Safety , 33 : 344
- Lévêque , J. P. , Ducros , G. Andreé , B. 1994 . “The HEVA Experimental Program,” . Nucl. Technol. , 108 : 33 – 44 .
- Ducros , G. , Malgouyres , P. P. Kissane , M. “Fission product release under severe accidental conditions; General presentation of the program and synthesis of VERCORS 1 to 6 results,” . Proc. Twenty-Seventh Water Reactor Safety Information Meeting . pp. 505 – 518 . NUREG/CP-0169
- Lewis , B. J. , Iglesias , F. C. Hunt , C. E. L. 1992 . “Release kinetics of volatile fission products under severe accident conditions,” . Nucl. Technol. , 99 : 330
- U. S. Nuclear Regulatory Commission . 1990 . Severe Accident Risks: An Assessment for Five U. S. Nuclear Power Plants NUREG- 1150
- 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. 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 . Portland . pp. 584 – 592 .
- Summers , R. M. , Cole , R. K. Smith , R. C. 1995 . MELCOR Computer Code Manuals NUREG/CR-6119
- Nakamura , T. , Hidaka , A. Hashimoto , K. 1999 . Research Program (VEGA) on the Fission Product Release from Irradiated Fuel JAERI-Tech 99–036
- Hidaka , A. , Kudo , T. Nakamura , T. 1999 . Current Status of VEGA Program and a Preliminary Test with Cesium Iodide JAERI-Research 99–066, [in Japanese]
- Hidaka , A. , Nakamura , T. Kudo , T. 2001 . Behavior of Radionuclides Release from Irradiated Fuel under Severe Accident Conditions [Results of VEGA-1 Tests] JAERI-Research 2001–055, [in Japanese]
- 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 .
- Hayashida , R. , Hidaka , A. Nakamura , T. 2001 . Operation and Maintenance Manuals for VEGA Apparatus on Radionuclide Release from Irradiated Fuel JAERI-Tech 2001–029, [in Japanese]
- 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 .
- Lorenz , R. A. and Osborne , M. F. 1995 . A Summary of ORNL Fission Product Release Tests with Recommended Release Rates and Diffusion Coefficients NUREG/CR-6261
- 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
- Kuhlman , D. J. , Lehmicke , D. J. and Meyer , R. O. 1985 . CORSOR User's Manual NUREG/CR-4173
- Bixler , N. E. 1998 . VICTORIA2.0, A Mechanical Model for Radionuclide Behavior in a Nuclear Reactor Coolant System Under Severe Accident Conditions NUREG/CR-6131
- Bird , R. B. , Stewart , W. E. and Lightfoot , E. N. 1960 . Transport Phenomena , New York , NY : John Wiley and Sons .