Published September 2007 | Version v1
Journal article

Thermalhydraulics studies examining the feasibility for introducing slightly enriched uranium fuel into the Embalse CANDU reactor

  • 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)

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.