Experimental and analytical modelling of a loss-of-pool-water accident in an SES-10 reactor
Description
An independent experimental program has been conducted at Carleton University to support and validate an analytical model of the thermalhydraulic behaviour of a 10 MW SLOWPOKE Energy System (SES-10) reactor in which the pool water is completely lost. The experimental results indicate that the entire height of the concrete pool wall is effective as a heat sink during the accident and that the analytical model, adapted to the experimental conditions, predicts the thermalhydraulic behaviour of the system quite well. Predictions of the analytical model, modified in the light of the experimental results, strongly reinforce the conclusions of an earlier study that the fuel and fuel sheath temperatures in an SES-10 in this low-probability accident will be low enough that no significant fuel damage will result and that there will be no significant fission product release. The analytical model can be applied to other pool-type reactors, such as a MAPLE reactor. (author) 9 refs., 2 tabs., 11 figs
Additional details
Additional titles
- Augmented title (English)
- SLOWPOKE Energy System
Publishing Information
- Imprint Title
- Proceedings of the Canadian Nuclear Society 15. annual conference
- Imprint Pagination
- [1000 p.].
- Journal Page Range
- (v.2) [17 p.].
- ISSN
- 0227-1907
- Report number
- INIS-mf--14987(v.1,2)
Conference
- Title
- 15. annual conference of the Canadian Nuclear Society; 34. annual conference of the Canadian Nuclear Association.
- Dates
- 5-8 Jun 1994.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28014360
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; L CODES; LOSS OF COOLANT; PROCESS HEAT REACTORS; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; SLOWPOKE TYPE REACTORS; TEST FACILITIES; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; POOL TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; WATER COOLED REACTORS; WATER MODERATED REACTORS