Published 1984
| Version v1
Book
Characteristics of residual two-phase pool in upper plenum during refill-reflood phase of BWR LOCA
Creators
Description
This paper deals with CCFL and CCFL breakdown phenomena associated with the injection of spray water into upper plenum during refill-reflood phase of BWR LOCA. It is found that when spray flow is slightly larger than the CCFL drainage determined by the core steam flow, pool maintains at some constant level near the spray elevation, after CCFL breakdown. On the other hand, when spray flow is appreciably larger than CCFL drainage, pool level slowly oscillates. TRAC-BD1 analysis of test results show the validity of sector simulation of test apparatus
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
- Journal Page Range
- p. B12-1-B1-2-9.
Conference
- Title
- International thermal hydraulics and plant operations topical meeting.
- Dates
- 22-24 Oct 1984.
- Place
- Taipei, TW (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17078704
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CORE FLOODING SYSTEMS; CORE SPRAY SYSTEMS; DRAINAGE; HEAT TRANSFER; HYDRAULICS; LEVELS; LOSS OF COOLANT; REACTOR PROTECTION SYSTEMS; STEAM; T CODES; TWO-PHASE FLOW; WATER
- Descriptors DEC
- ACCIDENTS; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS