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