Evaluation of advanced two-phase flow instrumentation in SCTF Core-1
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
In the Slab Core Test Facility (SCTF) Core-I, advanced two-phase flow instruments have been provided by the USNRC to measure the thermohydraulic behavior in the primary system including pressure vessel during the end of blowdown, refill and reflood phases of a postulated loss-of-coolant accident in a pressurized water reactor. The advanced instruments are turbine meters, drag disks, γ-densitometers, spool pieces, liquid level detectors (LLD), fluid distribution grids (FDG), impedance probes (flag, prong and string probes), film probes, and video optical probes. This report presents evaluated results of the data from these instruments. Some instruments are quantitatively evaluated by comparing with the data from the conventional instruments or the other advanced instruments. Main conclusions are as follows: (1) The spool pieces and the γ-densitometers work well and provide satisfactory results; (2) Some of the turbine meters, the impedance probes and the film probes give partially reasonable results, but still more improvements are required; (3) Most of the LLDs, the FDGs, the impedance probes, and the film probes do not work well due to a hard cable corrosion, and (4) The video optical probes give clear image of the flow pattern. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
16046393.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 156 p.
- Report number
- JAERI-M--84-065
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 16046393
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BLOWDOWN; CORE FLOODING SYSTEMS; DENSITOMETERS; FLOWMETERS; IMAGES; IMPEDANCE; LEVEL INDICATORS; LOSS OF COOLANT; MEASURING METHODS; OPTICAL SYSTEMS; PERFORMANCE; PWR TYPE REACTORS; REACTOR CORES; REACTOR INSTRUMENTATION; REACTOR SAFETY EXPERIMENTS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; FLUID FLOW; MEASURING INSTRUMENTS; PHOTOMETERS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS