MAAP 5.04 ex-vessel CRD tube heat transfer and melting model
Creators
Description
Highlights: • Enhancements are made to consider ex-vessel CRD housing heat transfer and melting. • The BWR Station Blackout (SBO) scenario was simulated using the new code. • The ex-vessel CRD tube heat transfer did not affect the time of vessel failure. - Abstract: Enhancements are made in the Boiling Water Reactor (BWR) version of MAAP 5.04 to consider ex-vessel Control Rod Drive (CRD) housing heat transfer and melting. The in-vessel CRD tube model is extended below the reactor vessel and conduction and radiative heat transfer between the lower head, CRD tubes, pedestal gas and pedestal wall are considered. The possibility of corium melt flowing into collapsed CRD tubes and causing creep rupture of CRD tubes outside the reactor vessel, leading to vessel failure, is considered. Lastly, ex-vessel CRD tube melting due to the corium jet exiting the breached reactor vessel after vessel failure is considered. The BWR Station Blackout (SBO) scenario was simulated using the new code. The results show that explicitly modeling the ex-vessel CRD tube heat transfer did not affect the time of vessel failure. Also, vessel failure due to corium ingress into ex-vessel CRD tubes was not predicted. A small, but nontrivial mass of steel from ablated ex-vessel CRD tubes was added to the debris bed on the pedestal floor after vessel failure.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.01.028Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.01.028;
- PII
- S0306-4549(16)30541-2;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 103
- Journal Page Range
- p. 265-274
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48086620
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; CONTROL ELEMENTS; CONTROL ROD DRIVES; CORIUM; HEAT TRANSFER; MELTING; REACTOR ACCIDENT SIMULATION; REACTOR VESSELS; RUPTURES; SEVERE ACCIDENTS; STATION BLACKOUT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.