GRABB—A Computer Code for Simulating Fission Gas Dispostion in Oxide Fuel During Fast Thermal Transient

REFERENCES

• H. MATZKE, “Gas Release Mechanisms in UO2-A Critical Review,” Radiat. Eff., 53, 219 (1980).
   Web of Science ®Google Scholar
• J. REST, “GRASS-SST: A Comprehensive, Mechanistic Model for the Prediction of Fission Gas Behavior in UO2-Base Fuels During Steady State and Transient Conditions,” NUREG/CR-0202, ANL-78-53, Argonne National Laboratory (June 1978).
   Google Scholar
• J. REST, “The Prediction of Transient Fission-Gas Release and Fuel Microcracking Under Severe Core-Accident Conditions,” Nucl. Technol., 56, 553 (1982).
   Web of Science ®Google Scholar
• C. C. DOLLINS and F. A. NICHOLS, “Swelling and Gas Release in UO2 at Low and Intermediate Temperatures,” J. Nucl Mater., 66, 143 (1977).
   Web of Science ®Google Scholar
• R. W. OSTENSEN, “F1SGAS—A Code for Fission Gas Migration and Fuel Swelling in an LMFBR Accident,” NUREG/CR-1124, SAND 78-1790, Sandia National Laboratories (Nov. 1979).
   Google Scholar
• J. R. MATTHEWS and W. H. WOOD, “A Simple Operational Gas Release and Swelling Model,” Nucl. Mater., 91, 241 (1980).
   Web of Science ®Google Scholar
• M. O. TUCKER and R. J. WHITE, CEGB Report, RD/B/N4425, Great Britain Central Electricity Generating Board, Berkeley Nuclear Laboratories, Bristol (1978).
   Google Scholar
• E. E. GRUBER, “Transient Fission Gas Swelling Due to Grain Boundary Bubble Growth,” Trans. Am. Nucl. Soc., 38, 371 (June 1981).
   Google Scholar
• S.-H. CHIEN, “Intragranular Fission Gas Behavior During Thermal Transient Simulation,” PhD Dissertation, University of California at Los Angeles (1980).
   Google Scholar
• J. A. TURNBULL and M. O. TUCKER, “Swelling on UO2 Under Conditions of Gas Release,” Philos. Mag. Suppl., 30, 47 (1974).
   Web of Science ®Google Scholar
• W. BEERE and G. L. REYNOLDS, “The Morphology and Growth of Interlinked Porosity of Irradiated UO2,” J. Nucl. Mater., 47, 51 (July 1973).
   Google Scholar
• P. J. CLEMM and J. C. FISHER, “The Influence of Grain Boundaries on the Nucleation of Secondary Phase,” Acta Metall., 3, 70 (1955).
   Google Scholar
• D. S. DUGDALE, “Yielding of Steel Sheets Containing Slits,” Mech. Phys. Solids, 8, 100 (1960).
   Web of Science ®Google Scholar
• M. O. TUCKER, “A Simple Description of Interconnected Grain Edge Porosity,” Nucl. Mater., 79, 190 (1979).
   Google Scholar
• S. M. GEHL, “Comparison of Fission-Gas Release and Mechanical Behavior During Transient Nuclear and Electrical Heating of Light-Water-Reactor Fuels,” NUREG/CR-1001, ANL-78-60, Argonne National Laboratory (June 1979).
   Google Scholar
• R. S. NELSON, “The Stability of Gas Bubbles in an Irradiation Environment,” Nucl. Mater., 31, 153 (1969).
   Web of Science ®Google Scholar
• C. A. HINMAN and O. D. SLAGLE, “Ex-Reactor Transient Fission Gas Release Studies, Fuel Pin PNL-2-4,” HEDL TME 77-83, UC 79b, Hanford Engineering Development Laboratory (May 1978).
   Google Scholar
• J. A. TURNBULL, “The Distribution of Intragranular Fission Gas Bubbles in UO2 During Irradiation,” J. Nucl. Mater., 28, 203 (1971).
   Google Scholar
• G. T. HAHN and A. R. ROSENF1ELD, “Local Yielding and Extension of a Crack Under Plane Stress,” Acta Metall., 13, 293 (1965).
   Google Scholar
• A. R. ROSEN FIELD, K. A. DAI, and G. H. HAHN, Proc. Int. Conf. Fracture, Sendai, Japan, A-179 (1965).
   Google Scholar
• J. F. BYRON “The Yield and Flow of Single Crystals of Uranium Dioxide,” Nucl. Mater., 28, 110 (1968).
   Web of Science ®Google Scholar
• S. CHANDRASEKHAR, “Stochastic Problems in Physics and Astronomy,” Rev. Mod. Phys., 15, 1 (1943).
   Google Scholar
• W. BEERE, “The Second Stage Sintering Kinetics of Powder Compacts,” Acta Metall., 23, 139 (1975).
   Google Scholar
• J. R. MATTHEWS, “The Initial Stages of Sintering and Hot-Pressing in Vibro-Compacted Fuels,”Nucl. Mater., 87 356(1979). ‘
   Google Scholar
• M. E. GULDEN, “Migration of Gas Bubbles in Irradiated Uranium Dioxide,” Nucl. Mater., 23, 30 (1967).
   Web of Science ®Google Scholar
• E. E. GRUBER, “Migration and Coalescence of Fission Gas Bubbles in Oxide Fuels by Surface Diffusion,” Proc. Int. Conf. Physical Metallurgy of Reactor Fuel Elements, Berkeley Nuclear Laboratories, Bristol (1973).
   Google Scholar
• W. M. ROBERTSON, “Surface Diffusion of Oxides,” Nucl. Mater., 30, 36 (1969).
   Web of Science ®Google Scholar
• B. J. BUESCHER and R. O. MEYER, “Helium Bubbles in Uranium Dioxide,” Nucl. Mater., 48, 143 (1972).
   Google Scholar
• P. G. SHEWMON, Trans. Am. Inst. Min. Metall. Pet. Eng., 230, 1134 (1964).
   Google Scholar
• M. J. F. NOTLEY and I. J. HASTINGS, “A Microstructure-Dependent Model for Fission Product Gas Release and Swelling in UO2 Fuel,” AW/. Eng. Des., 56, 163 (1980).
   Google Scholar
• M. J. F. NOTLEY and J. R. MacEWAN, “Stepwise Release of Fission Gas from UO2 Fuel,” Nucl. Appl., 2, 477 (Dec. 1966).
   Google Scholar