48
Views
3
CrossRef citations to date
0
Altmetric
Technical Paper

Fuel Performance and Fission Product Release Studies for Defected Fuel Elements

, , &
Pages 220-245 | Published online: 12 May 2017

References

  • P. T. TRUANT and I. J. HASTINGS, “CANDU Reactor Experience: Fuel Performance,” AECL-8774, Atomic Energy of Canada Limited (July 1985).
  • A. J. HAINS, R. L. DA SILVA, and P. T. TRUANT, “Ontario Hydro Fuel Performance Experience and Development,” Proc. Int. Conf. Candufuel, Chalk River, Canada, October 6–8, 1986, p. 79, Canadian Nuclear Society (1986).
  • R. D. MacDONALD, M. R. FLOYD, B. J. LEWIS, A. M. MANZER, and P. T. TRUANT, “Detecting, Locating and Identifying Failed Fuel in Canadian Power Reactors,” AECL-9714, Atomic Energy of Canada Limited (Feb. 1990).
  • R. L. YANG, O. OZER, and H. H. KLEPFER, “Fuel Performance Evaluation for EPRI Program Planning,” Proc. Int. Topi. Mtg. L WR Fuel Performance, Avignon, France, April 21–24, 1991, p. 258, American Nuclear Society (1991).
  • J. M. MARKOWITZ, “Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation,” WAPD-TM-351, Bettis Atomic Power Laboratory (May 1963).
  • D. H. LOCKE, “Defected Zircaloy Fuel,” Nucl. Eng. Int., p. 648 (Aug. 1969).
  • D. H. LOCKE, “The Behavior of Defective Reactor Fuel,” Nucl. Eng. Design, 21, 318 (1972).
  • D. H. LOCKE, “Mechanisms of Deterioration of Defected LWR Fuel,” Proc. Specialists’Mtg. Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Canada, September 17–21, 1979, IWGFPT/6, p. 101, International Atomic Energy Agency (1980).
  • R. A. PROEBSTLE, J. H. DAVIES, T. C. ROWLAND, D. R. RUTKIN, and J. S. ARMIJO, “The Mechanism of Defection of Zircaloy-Clad Fuel Rods by Internal Hydriding,” Proc. Topi. Mtg. Commercial Nuclear Fuel Technology Today, Toronto, Canada, April 28–30, 1975, American Nuclear Society (1975).
  • J. H. DAVIES, “Secondary Damage in LWR Fuel Following PCI Defection—Characteristics and Mechanisms,” Proc. Specialists’Mtg. Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Canada, September 17–21, 1979, IWGFPT/6, p. 135, International Atomic Energy Agency (1980).
  • B. COX, “Mechanism of Hydrogen Absorption by Zirconium Alloys,” AECL-8702, Atomic Energy of Canada Limited (Nov. 1984).
  • J. C. CLAYTON, “Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods,” Proc. 8th Int. Symp. Zirconium in the Nuclear Industry, STP 1023, p. 266, American Society for Testing and Materials (1989).
  • J. H. DAVIES and G. A. POTTS, “Post-Defect Behaviour of Barrier Fuel,” Proc. Int. Topi. Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 272, American Nuclear Society (1991).
  • R. L. DA SILVA, “Irradiation of a CANDU UO2 Fuel Element with Twenty-Three Machined Slits Cut Through the Zircaloy Sheath,” AECL-8260, Atomic Energy of Canada Limited (Sep. 1984).
  • M. R. FLOYD, “Characterisation of Defective CANDU Fuel Using Gaseous and Dissolved Fission Product Data,” CNS-IR-3735I-2, Ontario Hydro (Oct. 1985).
  • R. L. DA SILVA, D. R. McCRACKEN, and K. J. MONSERRAT, “Behaviour of Depositing Fission Products Released from Defective Fuel,” Advances in Ceramics, Fission Product Behavior in Ceramic Oxide Fuel, Vol. 17, p. 107, American Ceramic Society (1986).
  • B. J. LEWIS, C. R. PHILLIPS, and M. J. F. NOTLEY, “A Model for the Release of Radioactive Krypton, Xenon, and Iodine from Defective UO2 Fuel Elements,” Nucl. Technol., 73, 72 (1986).
  • B. J. LEWIS, D. B. DUNCAN, and C. R. PHILLIPS, “Release of Iodine from Defective Fuel Elements Following Reactor Shutdown,” Nucl. Technol., 77, 303 (1987).
  • B. J. LEWIS, “Fission Product Release from Nuclear Fuel by Recoil and Knockout,” J. Nucl. Mater., 148, 28 (1987).
  • B. J. LEWIS, “Fundamental Aspects of Defective Nuclear Fuel Behavior and Fission Product Release,” J. Nucl. Mater., 160, 201 (1988).
  • B. J. LEWIS, R. D. MacDONALD, and H. W. BONIN, “Release of Iodine and Noble Gas Fission Products from Defected Fuel Elements During Reactor Shutdown and Start-Up,” Nucl. Technol., 92, 315 (1990).
  • B. J. LEWIS, F. C. IGLESIAS, D. S. COX, and E. GHEORGHIU, “A Model for Fission Gas Release and Fuel Oxidation Behavior for Defected UO2 Fuel Elements,” Nucl. Technol., 92, 353 (1990).
  • B. J. LEWIS, “A Generalized Model for Fission-Product Transport in the Fuel-to-Sheath Gap of Defective Fuel Elements,” J. Nucl. Mater., 175, 218 (1990).
  • M. J. F. NOTLEY and J. H. K. LAU, “A Model for Estimating the Pre- and Post-Shutdown I-I31 Coolant Inventories in CANDU Reactors,” Proc. Int. Topi. Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 419, American Nuclear Society (1991).
  • B. J. LEWIS, R. J. GREEN, and C. W. T. CHE, “A Prototype Expert System for the Monitoring of Defected Nuclear Fuel Elements in Canada Deuterium Uranium Reactors,” Nucl. Technol., 98, 307 (1992).
  • R. DUTTON, “Hydrogen Embrittlement in Hydride-Forming Metals,” AECL-6272, Atomic Energy of Canada Limited (1978).
  • J. C. WOOD, “Interactions Between Stressed Zirconium Alloys and Iodine at 300°C,” J. Nucl. Mater., 23, 63 (1974).
  • J. F. ZIEGLER, J. P. BIERSACK, and U. LITTMARK, “The Stopping and Range of Ions in Solids,” Vol. 1, Pergamon Press, New York (1985); see also “TRIM-89: The Transport of Ions in Matter-Version 5.1,” International Business Machines (Nov. 1988).
  • D. R. OLANDER, “Fundamental Aspects of Nuclear Reactor Fuel Elements,” TID-26711-pl, p. 303, U.S. Department of Energy (1976).
  • C. WISE, “Recoil Release of Fission Products from Nuclear Fuel,” J. Nucl. Mater., 136, 30 (1985).
  • G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, p. 120, Robert E. Krieger, Huntington, New York (1979).
  • J. T. BITTEL, L. H. SJOHDAL, and J. F. WHITE, “Steam Oxidation Kinetics and Oxygen Diffusion in UO2 at High Temperatures,” J. Amer. Ceram. Soc., 52, 8, 446 (1968).
  • R. E. CARTER and K. W. LAY, “Surface-Controlled Oxidation-Reduction of UO2,” J. Nucl. Mater., 36, 77 (1970).
  • J. A. MEACHEN, “Oxygen Diffusion in Uranium Dioxide: A Review,” Nucl. Energy, 28, 221 (1989).
  • D. S. COX, E. C. IGLESIAS, C. E. L. HUNT, N. A. KELLER, R. D. BARRAND, J. R. MITCHELL, and R. F. O’CONNOR, “Oxidation of UO2 in Air and Steam with Relevance to Fission Product Releases,” Proc. Symp. Chemical Phenomenon Associated with Radioactivity During Severe Nuclear Plant Accidents, Anaheim, California, September 9–12, 1986, NUREG/CP-0078, p. 2, U.S. Nuclear Regulatory Commission.
  • D. S. COX, R. C. IGLESIAS, C. E. L. HUNT, R. R. O’CONNOR, and R. D. BARRAND, “High-Temperature Oxidation Behaviour of UO2 in Air and Steam,” Proc. Int. Symp. High-Temperature Oxidation and Sulphidation Processes, Hamilton, Ontario, Canada, August 26–30, 1990.
  • D. R. OLANDER, “Oxidation of UO2 by High-Pressure Steam,” Nucl. Technol., 74, 215 (1986).
  • P. O. PERRON, “Thermodynamics of Non-Stoichio-metric Uranium Dioxide,” AECL-3072, Atomic Energy of Canada Limited (May 1968).
  • B. COX, “Some Factors Which Affect the Rate of Oxidation and Hydrogen Absorption of Zircaloy-2 in Steam,” AERE-R4348, Atomic Energy Research Establishment (Nov. 1963).
  • G. W. PARRY and P. G. SMERD. “Review of PWR Fuel Rod Waterside Corrosion behavior,” NP-1472, Electric Power Research Institute (Aug. 1980).
  • H. STEHLE, E. GARZAROLLI, A. M. GARDE, and P. SMERD, “Characterization of ZrO2 Films Formed In-Reactor and Ex-Reactor to Study the Factors Contributing to the In-Reactor Waterside Corrosion of Zircaloy,” Proc. 6th Int. Symp. Zirconium in the Nuclear Industry, ASTM-STP 824, p. 483, American Society for Testing and Materials (1984).
  • H. R. PETERS, “Improved Characterization of Aqueous Corrosion Kinetics of Zircaloy-4,” Proc. 6th Int. Symp. Zirconium in the Nuclear Industry, ASTM-STP 824, p. 507, American Society for Testing and Materials (1984).
  • A. I. A. ALMARSHAD and A. C. KLEIN, “A Model for Waterside Oxidation of Zircaloy Fuel Cladding in Pressurized Water Reactors,” J. Nucl. Mater., 183, 186 (1991).
  • R. D. MacDONALD and J. J. LIPSETT, “The Behaviour of Defected Zircaloy-Clad-UO2 Fuel Elements with Graphite Coatings Between Fuel and Sheath Irradiated at Linear Powers of 48 kW/m,” AECL-6787, Atomic Energy of Canada Limited (May 1980).
  • R. D. MacDONALD, J. J. LIPSETT, E. E. PEREZ, and P. K. KOS, “Purposely Defected UO2 Zircaloy Fuel Elements Irradiated in Pressurized Light Water at Linear Powers of 55 kW/m,” AECL-7751, Atomic Energy of Canada Limited (May 1983).
  • A. H. BOOTH, “A Suggested Method for Calculating the Diffusion of Radioactive Rare Gas Fission Products from UO2 Fuel Elements and a Discussion of Proposed In-Reactor Experiments That May Be Used to Test Its Validity,” AECL-700, Atomic Energy of Canada Limited (Sep. 1957).
  • B. J. LEWIS and H. E. SILLS, “Fission-Product Transport and the Diffusion Approximation,” J. Nucl. Mater., 184, 107 (1991).
  • I. J. HASTINGS, C. E. L. HUNT, and J. J. LIPSETT, “Release of Short-Lived Fission Products from UO2 Fuel: Effects of Operating Conditions,” J. Nucl. Mater., 130, 407 (1982).
  • B. J. LEWIS, C. E. L. HUNT, and R. C. IGLESIAS, “Source Term of Iodine and Noble Gas Fission Products in the Fuel-to-Sheath Gap of Intact Operating Nuclear Fuel Elements,” J. Nucl. Mater., 172, 197 (1990).
  • B. J. LEWIS, D. B. KNIGHT, and R. C. IGLESIAS, “Comparison of the ANS 5.4 Fission Product Release Model with Sweep Gas Experiments,” Proc. Int. Topi. Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 605, American Nuclear Society (1991).
  • A. D. APPELHANS and J. A. TURNBULL, “Measured Release of Radioactive Xenon, Krypton and Iodine from UO2 During Nuclear Operation and a Comparison with Release Models,” Proc. 8th Water Reactor Safety Research Information Mtg., Gaithersburg, Maryland, October 27–31, 1980, U.S. Nuclear Regulatory Commission.
  • C. HELSTROM, “Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element,” AECU 3220 (July 1956).
  • Β. LUSTMAN, “Irradiation Effects in Uranium Dioxide,” Uranium Dioxide: Properties and Nuclear Applications, Chap. 9, p. 431, J. BELLE, Ed., U.S. Government Printing Office, Washington, D.C. (1961).
  • G. M. ALLISON and H. K. RAE, “The Release of Fission Gases and Iodine from Defected UO2 Fuel Elements of Different Lengths,” AECL-2206, Atomic Energy of Canada Limited (June 1965).
  • P. BOURGEOIS and J. P. STORA, “Behaviour of Fission Products in PWR Primary Circuits and Defected Fuel Rod Evaluation,” presented at the 5th Int. Conf. Structural Mechanics in Reactor Technology, Berlin, Germany, March 20, 1979.
  • P. BESLU, C. LEUTHROT, and G. FREJAVILLE, “PROFIP Code: A Model to Evaluate the Release of Fission Products from Defected Fuel in PWRs,” Proc. Specialists’ Mtg. Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Canada, September 17–21, 1979, IWGFPT/6, p. 23, International Atomic Energy Agency (1980).
  • R. BERAHA, G. BEUKEN, G. FREJAVILLE, C. LEUTHROT, and Y. MUSANTE, “Fuel Survey in the Light Water Reactors Based on the Activity of the Fission Products,” Nucl. Technol., 49, 426 (1980).
  • C. LEUTHROT, A. BRISSAUD, and J. P. MISSUD, “Relationships Between the Characteristics of Cladding Defects and the Activity of the Primary Coolant Circuit and Aid for the Management of Leaking Fuel Assemblies in PWR,” Proc. Int. Topl Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 324, American Nuclear Society (1991).
  • H. W. KALFSBEEK, “The Abundance of Fission Gases in the Off Gas of a Boiling Water Reactor,” Nucl. Technol., 62, 7 (1983).
  • J. T. MAYER, E. T. CHULICK, and V. SUBRAHMANYAM, “B&W Radiochemical Analyses for Defective Fuel,” Proc. Specialists’ Mtg. Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, Chalk River, Canada, September 17–21, 1979, IWGFPT/6, p. 221, International Atomic Energy Agency (1980).
  • H. ZÄNKER, “Defective Fuel Rod Detection in Operating Pressurized Water Reactors During Periods of Continuously Decreasing Fuel Rod Integrity Levels,” Nucl. Technol, U, 239 (1989).
  • D. L. BURMAN, “Methods for Estimating Numbers of Failed Rods from Coolant Activity Analysis,” presented at EPRI Workshop on Fuel Integrity Monitoring by Coolant Activity Analysis, Charlotte, North Carolina, May 21, 1986.
  • D. L. BURMAN, O. A. CORREAL, H. W. WILSON, H. KUNISHI, and L. H. BOMAN, “Development of a Coolant Activity Evaluation Model and Related Application Experience,” Proc. Int Topl Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 363, American Nuclear Society (1991).
  • C. E. BEYER, “Methodology Estimating Number of Failed Fuel Rods and Defect Size,” EPRI NP-6554, Electric Power Research Institute (Sep. 1989).
  • C. E. BEYER, “An Analytical Model for Estimating the Number and Size of Defected Fuel Rods in an Operating Reactor,” Proc. Int. Topl. Mtg. LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 437, American Nuclear Society (1991).
  • “MATPRO-Version 11 (Revision 1)-A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod behavior,” NUREG/CR-0497, U.S. Nuclear Regulatory Commission (1980).
  • H. MATZKE, “Gas Release Mechanisms in UO2-A Critical Review,” Radiat. Eff., 53, 219 (1980).
  • G. T. LAWRENCE, “A Review of the Diffusion Coefficient of Fission-Product Rare Gases in Uranium Dioxide,” J. Nucl. Mater., 71, 195 (1978).
  • M. J. F. NOTLEY, “ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements,” Nucl. Technol., 44, 445 (1979).
  • J. C. KILLEEN and J. A. TURNBULL, “An Experimental and Theoretical Treatment of the Release of *85Kr from Hyperstoichiometric Uranium Dioxide,” Proc. Workshop Chemical Reactivity of Oxide Fuel and Fission Product Release, Gloucestershire, England, April 7–9, 1987, p. 387, Central Electricity Generating Board.
  • J. V. SHARP, “Radiation Enhanced Diffusion,” Report 6267, Atomic Energy Research Establishment (1969).
  • A. B. LIDIARD, “Self-Diffusion of Uranium in UO2,” J. Nucl. Mater., 19, 106 (1966).
  • H. MATZKE, “Diffusion in Ceramic Oxide Systems,” Advances in Ceramics, Vol. 17, p. 1, American Ceramic Society (1986).
  • R. A. JACKSON and C. R. A. CATLOW, “Trapping and Solution of Fission Xenon in UO2; Part 1: Single Gas Atoms and Solution from Underpressurized Bubbles; and Part 2: Solution from Small Overpressurized Bubbles,” J. Nucl. Mater., 127, 161 (1985).
  • R. W. GRIMES and C. R. CATLOW, “The Stability of Fission Products in Uranium Dioxide,” Philos. Trans. R. Soc. London Ser. A, 335, 609 (1991).
  • E. SCHUSTER, F. GARZAROLLI, A. KERSTING, K. H. NEEB, and H. STEHLE, “Escape of Fission Products from Defective Fuel Rods of Light Water Reactors,” Nucl. Eng. Des., 64, 81 (1981).
  • G. KURKA, A. HARRER, and P. CHENEBAULT, “Fission Product Release from a Pressurized Water Reactor Defective Fuel Rod: Effect of Thermal Cycling,” Nucl. Technol., 46, 571 (1979).
  • R. J. LUTZ, Jr., “Iodine Behavior Under Transient Conditions in the Pressurized Water Reactor,” WCAP-8637, Westinghouse Electric Corporation (1975).
  • N. EICKELPASCH and R. HOCK, “Fission Product Release After Reactor Shutdown,” Proc. Symp. Experience from Operating and Fueling Nuclear Power Plants, Vienna, October 8–12, 1973, IAEA-SM-178/19, STI/Pub-351, International Atomic Energy Agency.
  • R. J. LUTZ and W. CHUBB, “Iodine Spiking-Cause and Effect,” Trans. Am. Nucl. Soc., 28, 649 (1978).
  • K. H. NEEB and E. SCHUSTER, “Iodine Spiking in PWRs: Origin and General behavior,” Trans. Am. Nucl. Soc., 28, 650 (1978).
  • N. EICKELPASCH, R. SEEPOLT, and R. HOCK, “Iodine Release Mechanism and Its Verification in Plant Operation,” Trans. Am. Nucl. Soc., 28, 652 (1978).
  • R. R. BELLAMY, “A Regulatory Viewpoint of Iodine Spiking During Reactor Transients,” Trans. Am. Nucl. Soc., 28, 651 (1978).
  • W. N. BISHOP, “Iodine Spiking,” EPRI NP-4595, Electric Power Research Institute (1986).
  • W. CHUBB, “On-Line Assessment of LWR Core Integrity,” Trans. Am. Nucl. Soc., 56, 508 (1988).
  • P. G. VOILLEQUE, “Measurements of Radioiodine Species in Samples of Pressurized Water Reactor Coolant,” Nucl. Technol., 90, 23 (1990).
  • J. P. ADAMS and C. L. ATWOOD, “The Iodine Spike Release Rate During a Steam Generator Tube Rupture,” Nucl. Technol., 94, 361 (1991).
  • G. M. ALLISON and R. R. J. ROBERTSON, “The Behaviour of Fission Products in Pressurized-Water Systems (A Review of Defect Tests on UO2 Fuel Elements at Chalk River),” AECL-1338, Atomic Energy of Canada Limited (Sep. 1961).
  • W. HÜTTIG, H. ZÄNKER, and M. FORBERG, “In-Core Surveillance of Defective PWR Fuel Elements in the Case of Fuel-to-Water Contact,” J. Nucl. Mater., 175, 147 (1990).
  • A. M. MANZER, “In-Core Assessment of Defective Fuel in CANDU-600 Reactors,” presented at IAEA Specialists’ Mtg. Post-Irradiation Examination and Experience, Tokyo, Japan, November 26–30, 1984.
  • A. M. MANZER and N. MACICI, “Fuel Defect Detection by Radioiodine Monitoring,” presented at 8th Annual Conf. Canadian Nuclear Society, Saint John, New Brunswick, June 14–17, 1987.
  • A. M. MANZER, R. W. SANCTON, and N. MACICI, “Canadian CANDU-600 Perspective on Fuel Integrity Performance Indicators,” Proc. Int. Mtg. Nuclear Power Plant Operation, Chicago, Illinois, August 30–September 3, 1987, AECL-9602, Atomic Energy of Canada Limited.
  • B. J. LEWIS, “A Model for Calculating the 1-131 Release from Defective Fuel for Steady-State and Reactor Shutdown Conditions,” Proc. 3rd Int. Conf. Candu Fuel, Pembroke, Canada, October 4–8, 1992, Canadian Nuclear Society (1992).
  • A. M. MANZER, “Transport Mechanisms of Uranium Released to the Coolant from Fuel Defects,” presented at Int. Conf. CANDU Fuel, Chalk River, Canada, October 6–8, 1986.
  • A. M. MANZER, J. W. D. ANDERSON, and C. W. SO, “Defect Detective: An Expert System for the Detection and Evaluation of Fuel Defects in CANDU 600 Nuclear Power Reactors,” presented at 9th Annual Conf. Canadian Nuclear Society, Winnipeg, Manitoba, June 12–15, 1988.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.