Published 1976
| Version v1
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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.
Files
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.