A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis
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A. El-Jaby, A Model for Predication Coolant Activity Behaviour for Fuel-failure Monitoring Analysis, Ph.D. Thesis, Royal Military College of Canada, March 2009.
C.E. Beyer, Methodology Estimating Number of Failed Fuel Rods and Defect Size, Electric Power Research Institute, EPRI NP-6554, September 1989.
C.E. Beyer, An analytical model for estimating the number and size of defected fuel rods in an operating reactor, in: Proceedings of the American Nuclear Society International Topical Meeting on LWR Fuel Performance, Avignon, France, April 21–24, 1991, p. 437.
D. Parrat, J.B. Genin, Y. Musante, C. Petit, A. Harrer, Failed rod diagnosis and primary circuit contamination level determination thanks to the DIADEME code – fuel failures in water reactors: causes and mitigation, in: Proceedings of a Technical Meeting held in Bratislava, Slovakia, 17–21 June, 2002, IAEA-TECDOC-1345, Part II, p. 265.
V. Likhanskii, I. Evdokimov, O. Khoruzhii, A. Sorokin, V. Novikov, Modelling of fission product release from defective fuel rods under WWER operating conditions and in leakage tests during refueling, in: Proceedings of the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, September 19–22, 2004, Paper 1083.
V.V. Likhanskii, I.A. Evdokimov, A.A. Sorokin, A.G. Khramov, V.D. Kanukova, O.V. Apollonova, A.V. Ugryumov, WWER Expert system for fuel failure analysis using data on primary coolant activity, in: Proceedings of the 2007 International LWR Fuel Performance Meeting, San Francisco, California, September 30–October 3, 2007, Paper 1067.
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, Atomic Energy of Canada Limited, 1957 [DCI-27 AECL-700].
A.H. Booth, A Method for Calculating Fission Gas Diffusion from UO2 Fuel and its Application to the X-2-f Loop Test, Atomic Energy of Canada Limited, 1957 [CRDC-721].
D.F. Shields, E.P. Penswick, R.D. Delaney, B.J. Lewis, Y.H. Kang, D.D. Semeniuk, Irradiation and Gamma-ray Spectroscopy Data for the High-powered, Porous End Plug Defect Experiment FFO-102-2, Atomic Energy of Canada Limited Report, Exp-FFO-10226, April 1982.
B.J. Lewis, Behaviour of a Zircaloy-sheathed UO2 Fuel Element Containing a Porous End Plug Defect and Exhibiting Secondary Sheath Hydriding Irradiated in Pressurized Light Water at a Linear Power of 67kW/m, Chalk River Nuclear Laboratories Report CRNL-2473, 1983.
R.L. da Silva, The Irradiation Performance of a Naturally Defective CANDU UO2 Fuel Element Power Cycled Between Linear Powers of 25–14kW/m and 38–22kW/m in the X-2 Loop of NRX, Chalk River Nuclear Laboratories Report CRNL-2674, September 1984.
R.L. da Silva, The Irradiation of a CANDU UO2 Fuel Element with Twenty-three Machined Slits Cut Through the Zircaloy Sheath, Atomic Energy of Canada Limited Report AECL-8260, September 1984.
R. Oduntan, F. Iglesias, R. Stone, J. Armstrong, B.J. Lewis, Using on-line monitoring of fission product data to manage reactor operations with in-core failed fuel elements, in: Proceedings of the Ninth International Conference on CANDU fuel, Belleville, Ontario, 18–21 September 2005.
K. Shaheen, A Semi-empirical Oxidation Model for Defective Nuclear Fuel, M.Sc. Thesis, Royal Military College of Canada, April 2008.