PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods

References

• M. J. BALL, “ORIGEN: The ORNL Isotope Generation and Depletion Code,” ORNL-4628, Oak Ridge National Laboratory (1973).
   Google Scholar
• U. FISHER and H. W. WIESE, KFK-3014, Kernforschungszentrum Karlsruhe (1973).
   Google Scholar
• M. SUZUKI and H. SAITO, “Light Water Reactor Fuel Analysis Code FEMAXI-IV Version 2,” JAERI-DATA/CODE, 97-043, Japan Atomic Energy Research Institute (Nov. 1997).
   Google Scholar
• D. D. LANNING, C. E. BEYER, and C. L. PAINTER, “FRAPCON-3: Modifications to Fuel Rod Material Properties and Performance Models for High-Burnup Application,” NUREG/CR-6534, PNNL-11513, Pacific Northwest National Laboratory (Oct. 1997).
   Google Scholar
• K. LASSMANN, “TRANSURANUS: A Fuel Rod Analysis Code Ready for Use,” J. Nucl. Mater., 188, 295 (1992).
   Web of Science ®Google Scholar
• K. LASSMANN, C. O’CARROLL, J. VAN DE LAAR, and C. T. WALKER, “The Radial Distribution of Plutonium in High Burnup UO2 Fuels,” J. Nucl. Mater., 208, 223 (1994).
   Web of Science ®Google Scholar
• K. LASSMANN, C. T. WALKER, and J. VAN DE LAAR, “Extension of the TRANSURANUS Burnup Model for Heavy Water Reactor Conditions,” J. Nucl. Mater., 255, 222 (1998).
   Web of Science ®Google Scholar
• J. L. MEEM, Two Group Reactor Theory, p. 274, Gordon and Breach, Science Publishers, New York (1964).
   Google Scholar
• Physics, Reactor Handbook, Vol. 3, Part A, H. SOODAK, Ed., Interscience Publishers, New York (1962).
   Google Scholar
• A. M. WEINBERG and E. P. WIGNER, The Physical Theory of Neutron Chain Reactors, p. 312, The University of Chicago Press, Chicago, Illinois (1958).
   Google Scholar
• E. D. ARNOLD, “Neutron Sources,” Engineering Compendium on Radiation Shielding, Vol. 1, p. 30, R. G. JAEGER, Ed., Springer-Verlag, New York (1968).
   Google Scholar
• J. C. STEWART and P. F. ZWEIFEL, “A Review of Self-Shielding Effects in the Absorption of Neutrons,” Proc. 2nd Int. Conf. Peaceful Uses of Atomic Energy, Geneva, Switzerland, Vol. 16, P/631, p. 650 (1958).
   Google Scholar
• S. F. MUGHABGHAB, “Neutron Resonance Parameters and Thermal Cross Sections,” Neutron Cross Sections, Vol. I, Part B, Academic Press, New York (1984).
   Google Scholar
• S. E. LEMEHOV, “Capabilities and Validation of the ASFAD Fuel Performance Code for WWER-440 High Burnup Fuel Rods,” Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, Portland, Oregon, March 2–6, 1997, p. 613, American Nuclear Society (1997).
   Google Scholar
• A. G. CROFF, M. A. BJERKE, G. W. MORRISON, and L. M. PETRI, “Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code,” ORNL/TM-6051, Oak Ridge National Laboratory (Sep. 1978).
   Google Scholar
• T. KAMEYAMA, T. MATSUMURA, and M. KINOSHITA, “Analysis of Rim Effect in High Burnup Fuel Irradiated in HBWR and Commercial LWR,” Proc. Enlarged HPG Mtg., Bolkesjø, Norway, February 11–16, 1990 (1990).
   Google Scholar
• J. SPINO, D. BARON, M. COQUERELLE, and A. D. STALIOS, “High Burn-Up Rim Structure: Evidences that Xenon-Depletion, Pore Formation and Grain Subdivision Start at Different Local Burn-Ups,” J. Nucl. Mater., 256, 189 (1998).
   Web of Science ®Google Scholar
• C. T. WALKER, M. COQUERELLE, W. GOLL, and R. MANZEL, “Irradiation Behaviour of MOX Fuel: Results of an EPMA Investigation,” Nucl. Eng. Des., 131, 1 (1991).
   Web of Science ®Google Scholar
• J. N. MORGAN and W-D. KREBS, “Siemens Experience with Large Scale Mixed Oxide Fuel Assembly Insertion in Light Water Reactors,” Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, West Palm Beach, Florida, April 17–21, 1994, p. 711, American Nuclear Society (1994).
   Google Scholar
• S. E. LEMEHOV, “Thermodynamic of the High Burnup UO2 Structure Formation and Fission Gas Release,” Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, Portland, Oregon, March 2–6, 1997, p. 523, American Nuclear Society (1997)
   Google Scholar