Large-scale multi-dimensional phenomena found in CCTF and SCTF experiment
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Thermal-hydraulic behaviors in pressure vessel during reflood phase of a PWR-LOCA are discussed based on the results from tests with Cylindrical Core and Slab Core Test Facilities, which model a 1100-MWe-class PWR with scaling ratio of about 1/20. Major findings on core thermal-hydraulics are, (i) much water accumulation in the upper part of the core, (ii) radially uniform water accumulations, and (iii) fluid circulation and/or concentration to high power bundles. These multi-dimensional phenomena cause better core cooling in high power bundle than expected from an evaluation model for licensing based on one-dimensional reflood experiments. The much water accumulation is considered to be caused by recirculation flow by comparing with data of the FLECHT low-flooding tests. Based on small scale reflood experiment, effect of local mass flow on heat transfer enhancement in a film boiling was correlated and all phenomena except the flow concentration effect were numerically well-simulated by using an analytical model with this correlation. The flow concentration effect on core heat transfer was empirically correlated with local power ratio. It was observed that non-uniform fluid mixing between core flow and subcooled water from hot legs for PWRs with combined-injection ECCS, which enhances the core coolability. This is multi-dimensional phenomena. The heat transfer enhancement was also well-simulated with the above-mentioned model. (authors). 15 figs., 20 refs
Additional details
Publishing Information
- Publisher
- Centre d'Etudes de Cadarache.
- Imprint Place
- Saint-Paul-lez-Durance (France)
- ISBN
- 2-72-72-0157-5
- Imprint Title
- Transient two-phase flow: ''Current issues in system thermal-hydraulics''
- Imprint Pagination
- 609 p.
- Journal Page Range
- p. 281-306.
Conference
- Title
- CSNI specialist meeting on transient two-phase flow.
- Dates
- 6-8 Apr 1992.
- Place
- Aix-en-Provence (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26053153
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; HYDRAULICS; LOSS OF COOLANT; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES; REWETTING; TEST FACILITIES; THERMODYNAMICS; VOID FRACTION; W CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DISTRIBUTION; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS