Thermalhydraulics studies examining the feasibility for introducing slightly enriched uranium fuel into the Embalse CANDU reactor
Creators
- 1. Atomic Energy of Canada Limited, Chalk River, Ont., K0J 1J0 (Canada)
- 2. Nucleoelectrica Argentina S.A., Buenos Aires (Argentina)
- 3. Atomic Energy of Canada Limited, Mississauga, Ont., L5K 1B2 (Canada)
Description
A joint study on the technical feasibility of using 0.9% slightly enriched uranium (SEU) fuel in the Embalse CANDU reactor was performed by Atomic Energy of Canada Limited (AECL) and Nucleoelectrica Argentina S.A. (NASA). The feasibility study focused on the following technical areas: reactor physics and fuel management, fuel performance, and safety. Part of the safety assessment involved detailed thermalhydraulics analyses of three accident scenarios for a full core of SEU fuel bundles: (i) slow loss-of-reactivity control (LORC) event (ii) large-break loss-of-coolant accident (LBLOCA) with emergency core cooling system (ECCS) available, and (iii) end-fitting failure. Other accident scenarios possibly encountered during the demonstration irradiation exercise or transition core have also been examined. It is concluded that introducing SEU fuel into the Embalse CANDU reactor is feasible. Clear advantages (e.g., fuel cost saving, increase in fuel exit burnup, and reduction in spent fuel volume) have been identified. The reduction in maximum bundle powers and the shift of the maximum bundle-power location to the inlet of the channel for the SEU fuel improve operating and safety margins. These margins are higher with the CANFLEX SEU fuel than the 37-element SEU fuel, due to lower linear powers and improved thermalhydraulic design
Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2007.02.028;
- PII
- S0029-5493(07)00235-X;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 237
- Journal Issue
- 15-17
- Journal Page Range
- p. 1628-1638
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 11. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-11
- Dates
- 2-6 Oct 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38090094
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC ENERGY OF CANADA LTD; BURNUP; CONTROL; DESIGN; DOUGLAS POINT ONTARIO REACTOR; ECCS; FAILURES; FEASIBILITY STUDIES; FUEL ELEMENT CLUSTERS; FUEL MANAGEMENT; IRRADIATION; LOSS OF COOLANT; PERFORMANCE; REACTIVITY; REACTOR PHYSICS; RISK ASSESSMENT; SAFETY MARGINS; SLIGHTLY ENRICHED URANIUM; SPENT FUELS
- Descriptors DEC
- ACCIDENTS; ACTINIDES; CANADIAN ORGANIZATIONS; CANDU TYPE REACTORS; ELEMENTS; ENERGY SOURCES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM; FUEL ASSEMBLIES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; PHWR TYPE REACTORS; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; URANIUM
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.