Recent study on two-dimensional thermal-hydraulic behavior in PWR core during the reflood phase of LOCA with the slab core test facility (SCTF)
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
To clarify the mechanism of two-dimensional core cooling behavior during the reflood phase, sensitivity of flooding rate to the core heat transfer and effect of the rod surface temperature were experimentally studied. An increased local flooding rate due to the flow convergence to the high power bundles seemed to be able to enhance the cooling of those bundles, especially in the latter portion of the transient. On the other hand, high temperature core was not cooled well although the higher temperature bundles were cooled down more effectively than the lower temperature bundles in each test, suggesting the importance of the indirect effect of the radial core temperature distribution on core cooling through the two-dimensional fluid behavior. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Soc. of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
- Imprint Pagination
- 1191 p.
- Journal Page Range
- p. 2/104-2/112.
Conference
- Title
- 2. international topical meeting on nuclear power plant thermal hydraulics and operations.
- Dates
- 15-17 Apr 1986.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18061796
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW RATE; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; REWETTING; THERMODYNAMICS; TIME DEPENDENCE; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS