Debris-bed quench characteristics under bottom-flood conditions
Creators
- 1. Dept. of Nuclear Energy, Brookhaven National Lab., Upton, NY 11973
Description
Light water reactor degraded core accident sequence studies postulate the existence of superheated core debris beds within the reactor vessel. From both the accident management viewpoint and the accident evaluation viewpoint, it is necessary to understand the quench characteristics of such a degraded core. In particular, the SCDAP code, which is intended to model the core response during a severe accident condition, must be able to predict the thermal-hydraulic state of the core as a function of time when the core is in a degraded (debris bed) state. At present, the SCDAP code does not have a debris bed quench model. This program is therefore geared towards developing such a model. The experimental part of the program aids in model development and provides a data base for verifying the transient debris bed quench models. The current work deals with the case of one-dimensional debris bed being quenched by the injection of liquid coolant at a constant rate from the bottom of the debris bed
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-121-5
- Imprint Title
- Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
- Journal Page Range
- p. VI3.1-VI3.8.
Conference
- Title
- International ANS/ENS topical meeting on thermal reactor safety.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080553
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLUMN PACKING; COMPUTERIZED SIMULATION; COOLING; DATA BASE MANAGEMENT; FLOODS; HYDRAULICS; MECHANICAL FRAGMENTATION; ONE-DIMENSIONAL CALCULATIONS; QUENCHING; REACTOR ACCIDENTS; REACTOR CORES; REACTOR PROTECTION SYSTEMS; RESPONSE FUNCTIONS; S CODES; THERMAL DEGRADATION; THERMODYNAMICS; THREE MILE ISLAND-2 REACTOR; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUNCTIONS; HEAT TREATMENTS; MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS