Heat transfer enhancement due to water accumulation near grid spacers during reflood
Creators
- 1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken
Description
Reflood experiments in a 36-rod bundle have been performed to investigate the effect of grid spacers on heat transfer and water accumulation behavior above the quench front. The heat transfer above grid spacers was significantly enhanced; the degree of enhancement was inversely proportional to the distance from the grid spacer in both dispersed and slug flows. In the dispersed flow region, a decrease of droplet diameter above the grid spacers, a rewetting of the spacer wall, and the onset of water accumulation above the grid spacers were observed. In the slug flow region, water accumulation just above the grid spacer was larger than below the grid spacer. Among parameters tested, the water accumulation in the core was mostly affected by the flooding rate
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-122-3
- Imprint Title
- Proceedings of third international topical meeting on reactor thermal hydraulics
- Journal Page Range
- p. 7.F1-7.F5.
Conference
- Title
- 3. international meeting on reactor thermal hydraulics.
- Dates
- 15-18 Oct 1985.
- Place
- Newport, RI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065750
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINERS; COOLING; CORE FLOODING SYSTEMS; DROPLETS; FUEL ELEMENT CLUSTERS; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; HYDRAULICS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; SPACERS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ECCS; ENERGY TRANSFER; FUEL ASSEMBLIES; PARTICLES; REACTOR PROTECTION SYSTEMS; SAFETY; SIMULATION