An analysis of molten-corium-induced failure of drain pipes in BWR Mark 2 containments
Creators
- 1. Oak Ridge National Lab., TN (USA)
- 2. Rensselaer Polytechnic Inst., Troy, NY (USA)
Description
This study has focused on mechanistic simulation and analysis of potential failure modes for inpedestal drywell drain pipes in the Limerick boiling water reactor (BWR) Mark 2 containment. Physical phenomena related to surface tension breakdown, heatup, melting, ablation, crust formation and failure, and core material relocation into drain pipes with simultaneous melting of pipe walls were modeled and analyzed. The results of analysis have been used to assess the possibility of drain pipe failure and the resultant loss of pressure-suppression capability. Estimates have been made for the timing and amount of molten corium released to the wetwell. The study has revealed that significantly different melt progression sequences can result depending upon the failure characteristics of the frozen metallic crust which forms over the drain cover during the initial stages of debris pour. Another important result is that it can take several days for the molten fuel to ablate the frozen metallic debris layer -- if the frozen layer has cooled below 1100 K before fuel attack. 10 refs., 3 figs., 4 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91011365; NTIS; INIS; US Govt. Printing Office Dep.Files
22085554.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- CONF-910739--13
Conference
- Title
- ASME/AIChE/ANS national heat transfer conference.
- Dates
- 26-31 Jul 1991.
- Place
- Minneapolis, MN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085554
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABLATION; B CODES; COMPUTERIZED SIMULATION; CORIUM; FAILURE MODE ANALYSIS; HEAT TRANSFER; HYDRAULICS; LIMERICK-2 REACTOR; MELTDOWN; MOLTEN METAL-WATER REACTIONS; PIPES; PRESSURE VESSELS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; STEELS; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; ALLOYS; BWR TYPE REACTORS; CARBON ADDITIONS; COMPUTER CODES; CONTAINERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; METALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (USA); Nuclear Regulatory Commission, Washington, DC (USA).