Matrix database of EPRI experimental projects on small-break loss-of-coolant accidents
- 1. Intermountain Technologies, Inc., Idaho Falls, ID (USA)
Description
The large break LOCA had been studied extensively for many years and substantial analytical methods had been developed and verified for evaluation of this DBA. The nature of the physical processes which occur during a SBLOCA are significantly different than those which occur in a DBA LOCA, especially for a pressurized water reactor (PWR). As a result, only a portion of the methods developed for large break LOCA evaluation were applicable to SBLOCA, and a new list of research priorities arose out of questions raised during the evaluation of TMI-2. The nuclear safety research and development program at EPRI responded to the industry's need for improved understanding of SBLOCA. Projects to investigate SBLOCA that were in place prior to the TMI-2 accident were augmented and new projects were implemented. The overall cope of EPRI SBLOCA projects include both analytical development and experimental work. This report focuses on the experimental work sponsored by EPRI to support improved understanding of the SBLOCA. All of the EPRI experimental projects which relate to SBLOCA, both prior to and following TMI-2, were reviewed and the results summarized in an attempt to provide an overall matrix oriented view of the EPRI SBLOCA experimental database. 5 tabs
Availability note (English)
Available from Research Reports Center, Box 50490, Palo Alto, CA 94303.Additional details
Additional titles
- Subtitle (English)
- Final report
Publishing Information
- Imprint Pagination
- 123 p.
- Report number
- EPRI-NP--6180
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21014132
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CLOSED-CYCLE SYSTEMS; DATA BASE MANAGEMENT; EXPERIMENT PLANNING; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATRICES; PROGRESS REPORT; PWR TYPE REACTORS; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; MANAGEMENT; PLANNING; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS