Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants
International Atomic Energy Agency, Dec 22, 2003 - Business & Economics - 64 pages
This report captures the common features and differences between Western PWR and WWER fuel, and may serve as a general basis for the sefety evaluation of these fuels. Therefore, it should be very beneficial for PWR and WWER licensing activities, as it focuses on the issues of importance for the review of fuel safety cases.
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DESCRIPTION OF THE CRITERIA APPLIED IN THE EAST AND IN THE WEST
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boron cal/g cladding diameter Conclusions control rod coolable coolant activity core design core monitoring systems critical heat flux crud deposition Description and rationale design criterion design limits DNB operating limit DNB safety limit DNBR embrittlement enthalpy evaluation fretting wear fuel design fuel failure limit fuel rods fuel safety criteria fuel safety related fuel vendor gap activity high burnup hold-down force IAEA intermediate mast internal gas pressure Item B-6 Item C-2 LHGR licensing approach limit values Limiting cladding limits are defined loads LOCA MWd/kg normal operation Nuclear OECD oxidation PCMI plant operation plastic deformation power distribution power peaking PWR and WWER radial peaking factor rationale No difference reactivity coefficient Recommendations reload design Russian Federation safety related criteria source term spacer strain stress corrosion cracking support grid tailpiece technical specifications transients verified western PWR western reactors workshops WWER fuel WWER operating countries WWER reactors Zircaloy