LWR steam spike phenomenology: debris bed quenching experiments
Description
An experimental investigation is reported whose objective is to provide an understanding of the thermal interaction between superheated core debris and water during postulated light-water reactor degraded core accidents. The experiment was designed to study the heat transfer characteristics of superheated spheres as they are quenched in a packed bed configuration by an overlying pool of water. The results of the experiment are applied to understanding of the containment steam spike phenomenon. Three-millimeter stainless steel spheres were heated in an oven to temperatures between 533 and 9770K, and subsequently transferred to a vertical 108.2 mm i.d. stainless steel vessel. Water at temperatures between 2740K and 3600K was released on to the spheres and the resulting thermal interaction was observed. Packed beds were studied whose nominal heights were in the range 200 mm to 400 mm. The experiments were carried out at constant pressure, with the steam vented to the atmosphere. Bed and wall temperature traces are presented for a range of experimental conditions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01 as DE83003593.
Files
Additional details
Publishing Information
- Imprint Pagination
- 82 p.
- Report number
- NUREG/CR--2857
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14755050
- 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; FAILURES; HEAT TRANSFER; HYDRAULICS; MELTDOWN; MOLTEN METAL-WATER REACTIONS; PRESSURE GRADIENTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; STEAM; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- BNL-NUREG--51571.