Published June 1998 | Version v1
Report Open

Addressing severe accidents in the CANDU 9 design

  • 1. Atomic Energy of Canada Ltd, Mississauga, Ontario (Canada)

Description

CANDU 9 is a single-unit evolutionary heavy-water reactor based on the Bruce/Darlington plants. Severe accident issues are being systematically addressed in CANDU 9, which includes a number of unique features for prevention and mitigation of severe accidents. A comprehensive severe accident program has been formulated with feedback from potential clients and the Canadian regulatory agency. Preliminary Probabilistic Safety Analyses have identified the sequences and frequency of system and human failures that may potentially lead to initial conditions indicating onset of severe core damage. Severe accident consequence analyses have used these sequences as a guide to assess passive heat sinks for the core, and containment performance. Estimates of the containment response to mass and energy injections typical of postulated severe accidents have been made and the results are presented. We find that inherent CANDU severe accident mitigation features, such as the presence of large water volumes near the fuel (moderator and shield tank), permit a relatively slow severe accident progression under most plant damage states, facilitate debris coolability and allow ample time for the operator to arrest the progression within, progressively, the fuel channels, calandria vessel or shield tank. The large-volume CANDU 9 containment design complements these features because of the long times to reach failure

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Part of:
Design measures for prevention and mitigation of severe accidents at advanced water cooled reactors. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Design measures for prevention and mitigation of severe accidents at advanced water cooled reactors. Proceedings of a technical committee meeting
Imprint Pagination
230 p.
Journal Page Range
p. 167-184
ISSN
1011-4289
Report number
IAEA-TECDOC--1020

Conference

Title
IAEA technical committee meeting on impact of severe accidents on plant design and layout of advanced water cooled reactors
Dates
21-25 Oct 1996
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
29045550
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; CONTAINMENT; DESIGN; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; THERMAL REACTORS

Optional Information

Notes
5 refs, 17 figs, 1 tab