Fission Product Releases at Severe Light Water Reactor Accident Conditions: ORNL/CEA Measurements Versus Calculations

References

• R. A. LORENZ, J. L. COLLINS, A. P. MALINAUSKAS, O. L. KIRKLAND, and R. L. TOWNS, “Fission Product Release from Highly Irradiated LWR Fuel”, NUREG/CR-0722 (ORNL/NUREG/TM-287/R2), Oak Ridge National Laboratory (Feb. 1980).
   Google Scholar
• R. A. LORENZ, J. L. COLLINS, A. P. MALINAUSKAS, M. F. OSBORNE, and R. L. TOWNS, “Fission Product Release from Highly Irradiated LWR Fuel Heated to 1300-1600°C in Steam”, NUREG/CR-1386 (ORNL/NUREG/TM-346), Oak Ridge National Laboratory (Nov. 1980).
   Google Scholar
• R. A. LORENZ, J. L. COLLINS, M. F. OSBORNE, R. L. TOWNS, and A. P. MALINAUSKAS, “Fission Product Release from BWR Fuel Under LOCA Conditions”, NUREG/CR-1773 (ORNL/NUREG/TM-388), Oak Ridge National Laboratory (July 1981).
   Google Scholar
• M. F. OSBORNE, J. L. COLLINS, R. A. LORENZ, J. R. TRAVIS, and C. S. WEBSTER, “Design, Construction, and Testing of a 2000°C Furnace and Fission Product Collection System”, NUREG/CR-3715 (ORNL/TM-9135), Oak Ridge National Laboratory (Sep. 1984).
   Google Scholar
• M. F. OSBORNE, J. L. COLLINS, and R. A. LORENZ, “Experimental Studies of Fission Product Release from Commercial LWR Fuel Under Accident Conditions,” Nucl. Technol., 78, 157 (1987).
   Web of Science ®Google Scholar
• M. F. OSBORNE, J. L. COLLINS, P. A. HAAS, R. A. LORENZ, J. R. TRAVIS, and C. S. WEBSTER, “Design and Final Safety Analysis Report for Vertical Furnace Fission Product Release Apparatus in Hot Cell B, Building 4501”, NUREG/CR-4332 (ORNL/TM-9270), Oak Ridge National Laboratory (Mar. 1986).
   Google Scholar
• J. L. COLLINS, M. F. OSBORNE, R. A. LORENZ, and A. P. MALINAUSKAS, “Fission Product Iodine and Cesium Release Behavior Under LWR Accident Conditions,” Nucl. Technol., 81, 78 (1988).
   Web of Science ®Google Scholar
• J. L. COLLINS, M. F. OSBORNE, and R. A. LORENZ, “Fission Product Tellurium Release Behavior Under Severe Light Water Reactor Accident Conditions,” Nucl. Technol., 77, 18 (1987).
   Web of Science ®Google Scholar
• A. G. CROFF, “ORIGEN2 —A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code”, ORNL-5621, Oak Ridge National Laboratory (July 1980).
   Google Scholar
• M. F. OSBORNE and R. A. LORENZ, “ORNL Studies of Fission Product Release Under Severe LWR Accident Conditions,” Nucl. Saf., 33-3, 344 (May 1993).
   Google Scholar
• F. C. IGLESIAS, C. E. L. HUNT, F. GARISTO, and D. S. COX, “Ruthenium Release Kinetics from Uranium Oxides,” Proc. Conf. Fission Product Transport Process in Reactor Accidents, Dubrovnik, Yugoslavia, May 22–26, 1989, p. 187, Hemisphere Publishing Corp., New York (1990).
   Google Scholar
• M. F. OSBORNE and R. A. LORENZ, “Results of ORNL VI Series Fission Product Release Tests,” Proc. 20th Water Reactor Safety Information Mtg., Bethesda, Maryland, October 21–23, 1992.
   Google Scholar
• M. R. KUHLMAN, D. J. LEHMICKE, and R. O. MEYER, “CORSOR User’s Manual”, NUREG/CR-4173, U.S. Nuclear Regulatory Commission (Jan. 1985).
   Google Scholar
• M. RAMAMURTHI and M. R. KUHLMAN, “Refinement of CORSOR —An Empirical In-Vessel Fission Product Model”, U.S. Nuclear Regulatory Commission (Oct. 31, 1990).
   Google Scholar
• T. NAKAMURA and R. A. LORENZ, “A Study of Cesium and Krypton Releases Observed in HI and VI Tests Using a Booth Diffusion Model”, Oak Ridge National Laboratory, Private Communication (1993).
   Google Scholar
• R. A. LORENZ and M. F. OSBORNE, “A Summary of ORNL Fission Product Release Tests with Recommended Release Rates and Diffusion Coefficients”, NUREG/CR-6261 (ORNL/TM-12801), Oak Ridge National Laboratory (July 1995).
   Google Scholar
• D. POWERS, “Release of Fission Product and Generation of Aerosols During the In-Vessel Phases of a Severe Reactor Accident”, Sandia National Laboratories (1985).
   Google Scholar
• M. F. OSBORNE, J. L. COLLINS, R. A. LORENZ, J. R. TRAVIS, C. S. WEBSTER, and T. NAKAMURA, “Data Summary Report for Fission Product Release Test VI-4”, Oak Ridge National Laboratory (Sep. 1989).
   Google Scholar
• “Reactor Safety Study —An Assessment of Accident Risk in U.S. Commercial Nuclear Power Plants”, WASH 1400 (NUREG-75/014), U.S. Nuclear Regulatory Commission (Oct. 1975).
   Google Scholar
• AMERICAN NUCLEAR SOCIETY WORKING GROUP 5.4, “Background and Derivation of ANS Standard Fission Product Release Model,” NUREG/CR-2507, U.S. Nuclear Regulatory Commission (Jan. 1982).
   Google Scholar