Experimental system description for air-water CCFL tests of the 161-rod FLECHT-SEASET test vessel upper plenum
Description
A series of countercurrent flow limiting (CCFL) experiments has been performed by EG and G Idaho, Inc. in the Steam-Air-Water (SAW) test facility at the Idaho National Engineering Laboratory on behalf of the US Nuclear Regulatory Commission (NRC). Tests were performed in a mockup of the vessel for the 161-Rod Systems Effects Test (SET) facility of the FLECHT-SEASET program, conducted by the Westinghouse Electric Corporation. Westinghouse and the NRC will use the test results to provide a CCFL correlation to predict the flooding behavior in the upper plenum of the SET vessel. This paper presents a description of the experimental system and the test conduct, including data validation and uncertainty analysis. The test objectives centered on experimentally obtaining coefficients in the Wallis correlation for flooding with the specific vessel geometry. The test conditions and vessel configuration are described and the design of the test loop, instrumentation, and data acquisition are discussed. The establishment of a test point and the resultant data are described
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83013668.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- EGG-M--04283
Conference
- Title
- 3. multi-phase flow and heat transfer symposium.
- Dates
- 18-20 Apr 1983.
- Place
- Miami, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792284
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-830439--10.