Published January 1976 | Version v1
Report Restricted

Blowdown heat transfer phenomena in the scaled BWR test system

Creators

Description

Experimental results from the Boiling Water Reactor (BWR) blowdown heat transfer program (BDHT), obtained in the BWR scaled-test apparatus, are used to provide a basis for evaluating BDHT phenomena. BWR loss-of-coolant accident (LOCA) analysis using the current BWR LOCA evaluation method, when applied to the test apparatus, shows a substantial margin in the prediction of peak cladding temperature. Observed thermal-hydraulic and heat transfer phenomena are evaluated and compared with the current method. Specific phenomenologically based model refinements are recommended for break flow, void distribution, and heat transfer

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
26 p.
Report number
GEAP--21126

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7268744
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BLOWDOWN; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; DATA; FLUID FLOW; HEAT TRANSFER; LOSS OF COOLANT; MATHEMATICAL MODELS; MOCKUP; TESTING
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; INFORMATION; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Available from NTIS. $5.00.