Model for superheated debris-bed quench for severe-accident containment calculations
Description
Core meltdown accidents are being analyzed to develop an understanding of the risk associated with such postulated accidents and to evaluate the impact of possible mitigating engineering safety equipment. An integral feature of these analyses is the determination of containment building pressurization as a result of loadings imposed by the energy stored in the molten core debris. A major source of containment pressurization would result from the ex-vessel thermal interaction between molten core debris and water available beneath the reactor vessel. It has been suggested that the thermal interaction would occur in two stages: (1) the melt fall period during which the melt mixes with water, breaks up and transfers energy to the coolant, and (2) the debris bed or molten pool quench period during which the core debris rests on the concrete beneath the vessel and is cooled by an overlying pool of water. This paper is directed towards development of models to predict the thermal-hydraulic characteristics of superheated beds of solidified core debris which are cooled by water supplied by an overlying pool of water
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83017586.Files
15001921.pdf
Files
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Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- BNL-NUREG--33574
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15001921
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CORIUM; HEAT TRANSFER; HYDRAULICS; MELTDOWN; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS