Published 1988 | Version v1
Book

Probabilistic risk assessment study of a CANDU 600

  • 1. Atomic Energy of Canada Ltd, Mississauga, Ontario (Canada)
  • 2. Carleton Univ., Ottawa, Ontario (Canada)
  • 3. N.V. Tot Keuring van Elektrotechnische Materialen, Arnhem (Netherlands)

Description

The paper summarizes the methodology, phenomenology and results relevant to the assessment of severe events in a CANDU 600 station. The station design being analysed is a CANDU 600 currently operating in Canada. This evaluation includes event frequency and fission product release assessments but does not include dose assessments, so that the information is equivalent to a level 2 PRA. The study has shown that the predicted frequency for core melt in a CANDU is fairly low (4.6x10-6 events/year). This is due in large part to the heavy water moderator which acts as a heat sink, prevents UO2 melting and maintains core geometry for many events which could otherwise turn into a core melt. The consequences for most core melts will be limited to the release of a fraction of noble gases and organic iodides. Other isotopes will be condensed or dissolved in the containment atmosphere and will, after some time, end up in the pool of water in the basement, unavailable for release. The frequency and consequences of less likely, more severe core melt sequences are also discussed in the paper and shown to be small contributors to public risk. (author). 9 refs, 2 figs, 1 tab

Part of:
Severe accidents in nuclear power plants. V.1

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020188-1
Imprint Title
Severe accidents in nuclear power plants
Imprint Pagination
505 p.
Series
Proceedings series.
Journal Page Range
v. 1 p. 245-262.

Conference

Title
International symposium on severe accidents in nuclear power plants.
Dates
21-25 Mar 1988.
Place
Sorrento (Italy).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
20006410
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; FISSION PRODUCT RELEASE; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; RISK ASSESSMENT; TRANSIENTS
Descriptors DEC
ACCIDENTS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information

Secondary number(s)
IAEA-SM--296/5.