Core liquid level depression in 5% small break LOCAs: an investigation using subscale data
- 1. EG and G Idaho, Inc., Idaho Falls (USA)
Description
Core heatup has been shown to be possible, during the course of small break loss-of-coolant accidents (SBLOCAs), even when sufficient inventory is present to fully cover the rods with a two-phase mixture. Such behavior occurs when steam, trapped between the loop seal and the core inventory, moves coolant out of the core barrel region and uncovers the rod upper elevations. The net result is core liquid level depression. Core liquid level depression and subsequent core heatups are investigated using subscale data from the ROSA-IV Program's 1/48-scale Large Scale Test Facility (STF) and the 1/1705-scale Semiscale facility. The depression phenomena and factors which influence the minimum core level are described and illustrated using examples from the data. Analyses conducted using the TRAC-PF1/MOD1 version 12.7 thermal-hydraulic code are also described and summarized
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 4, Separate effects/experiments and analyses, Source term uncertainty analysis, Integral systems testing, 2D/3D research
- Journal Page Range
- p. 463-480.
- Report number
- NUREG/CP--0091-Vol.4
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20019270
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DATA; FLOW BLOCKAGE; FLOW MODELS; FLUID FLOW; HEATING; JAPAN; LEVEL INDICATORS; LOSS OF COOLANT; PERFORMANCE TESTING; REACTOR CORES; REACTOR SAFETY; STEAM; T CODES; TEST FACILITIES; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; ASIA; COMPUTER CODES; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL MODELS; MEASURING INSTRUMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS