Published 1976 | Version v1
Report Restricted

PWR-blowdown heat transfer separate effects program

Description

The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results are obtained from the Thermal-Hydraulic Test Facility (THTF). Supporting experiments are carried out in several additional test loops - the Forced Convection Test Facility (FCTF), an air-water loop, a transient steam-water loop, and a low-temperature water mockup of the THTF heater rod bundle. The studies to date are described

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
61 p.
Report number
CONF-760954--1

Conference

Title
4. water reactor safety research information meeting.
Dates
27 Sep 1976.
Place
Washington, District of Columbia, United States of America (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8312887
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BLOWDOWN; CRITICAL HEAT FLUX; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MOCKUP; PWR TYPE REACTORS; RESEARCH PROGRAMS; TESTING
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; HEAT FLUX; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Available from NTIS. $4.50.