Published 1983 | Version v1
Report Restricted

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.

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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.