Published December 1996 | Version v1
Report Open

Passive heat removal in CANDU

  • 1. AECL CANDU, Sheridan Park Research Community, Mississauga, ON (Canada)

Description

The Three Mile Island accident spurred a world-wide interest in severe accidents. The initial reaction was to increase the preventative measures in existing designs, followed by development of predictive capabilities to improve the management of severe accidents. Recently, emphasis has been placed in new designs on mitigative measures which slow down or contain the progression of a severe accidents. U.S. requirements for Advanced Light Water Reactor designs must now: provide reactor cavity floor space to enhance debris spreading; provide a means to flood the reactor cavity to assist in the cooling process. The paper describes how CANDU Pressurized Heavy Water Reactors (PHWRs) have severe accident prevention and mitigation inherent in the design; in particular, the U.S. severe accident requirements can be met without significant change to the design of current CANDUs. (author). 32 refs, 7 figs, 1 tab

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Part of:
Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

Additional details

Publishing Information

Imprint Title
Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting
Imprint Pagination
357 p.
Journal Page Range
p. 145-160.
ISSN
1011-4289
Report number
IAEA-TECDOC--920

Conference

Title
Advisory group meeting on technical feasibility and reliability of passive safety systems for nuclear power plants.
Dates
21-24 Nov 1994.
Place
Juelich (Germany).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28021870
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; CANDU TYPE REACTORS; DESIGN; MANAGEMENT; MITIGATION; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ENGINEERING
Descriptors DEC
ACCIDENTS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS

Optional Information