Direct containment heating calculations for Ringhals 3
Creators
- 1. Swedish State Power Board, Vaellingby (Sweden)
- 2. Winfrith Technology Centre, Dorchester, Dorset (United Kingdom)
Description
The Swedish nuclear power program consists of 12 power reactors. Nine of these are BWR:s and three are PWR:s. At the Ringhals site on the west coast of Sweden we have one BWR and three PWR:s (three-loop Westinghouse design). Direct Containment Heating (DCH) is a severe accident scenario in which a significant part of the core debris after melt-through of the reactor vessel is dispersed into the containment causing a rapid increase of the temperature and pressure in the containment atmosphere. Under certain assumptions concerning the accident sequence DCH is predicted to be a threat to the integrity of the PWR containment. However, the results of such DCH analyses are dependent on the choice of key modelling parameters in the calculations. Finally different plants must be treated individually mainly due to different failure pressure of the containment but also specific design of the containment. (author). 6 refs., 2 tabs., 2 figs
Additional details
Publishing Information
- ISBN
- 0-919784-21-6; 0-919784-22-4
- Imprint Title
- Proceedings of the 2. international conference on containment design and operation. Vol. 1,2
- Imprint Pagination
- [1326 p.].
- Journal Page Range
- [11 p.].
- Report number
- INIS-mf--14838
Conference
- Title
- 2. International conference on containment design and operation.
- Dates
- 14-17 Oct 1990.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 27066157
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; CONTAINMENT; MATHEMATICAL MODELS; MELTDOWN; MITIGATION; PRESSURIZATION; REACTOR CORE DISRUPTION; REACTOR SAFETY EXPERIMENTS; RINGHALS-3 REACTOR; SAFETY ANALYSIS; SIMULATION; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS