Published 1988 | Version v1
Book

Severe accident mitigating measures in the Ringhals and Forsmark plants and resulting reduction of the source term

  • 1. Swedish State Power Board, Vaellingby (Sweden)

Description

In the paper the severe accident mitigating measures in the Ringhals and Forsmark plants are outlined. A strong emphasis is put on both hardware and procedural measures to ensure that the reactor is brought back to a stable cooling state and that the containment integrity will not be endangered. Specific measures to protect the BWRs in the early stage of an accident sequence will be implemented such as protection of penetrations from molten core debris and the possibility to vent the containment in the case of a loss of coolant accident combined with the loss of pressure suppression function. An important part of the envisaged strategy after vessel melt-through is to supply water to the containment as soon as possible to avoid pressure build-up, to wash out aerosols and to reach a final stable state by covering the remaining core with water. In the case of a late pressure build-up a filtered vent will limit the release of radioactive products to less than 0.1% of the core inventory of Cs and I in a 1800 MWt reactor according to the requirements by the Swedish government. The analysis performed so far has shown that this limit is met with a wide margin. (author). 2 refs, 3 figs

Part of:
Nuclear power performance and safety. V.4.: Safety technology

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-050388-8
Imprint Title
Nuclear power performance and safety. V.4.: Safety technology
Imprint Pagination
651 p.
Series
Proceedings series.
Journal Page Range
v. 4 p. 225-232.

Conference

Title
International conference on nuclear power performance and safety.
Dates
28 Sep - 2 Oct 1987.
Place
Vienna (Austria).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
20042347
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; MANAGEMENT; MELTDOWN; SAFETY ENGINEERING; SOURCE TERMS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
IAEA-CN--48/114.