Published 1977
| Version v1
Book
Loss-of-Fluid Test (LOFT) facility
Description
LOFT is a well instrumented scaled model of a commercial pressurized water reactor. It is designed to study the behavior of engineered safety systems such as emergency core cooling systems during reactor accident conditions. LOFT, the current nonnuclear experiment series and the forthcoming nuclear experiments, are described. Significant nonnuclear experimental results are reported
Additional details
Publishing Information
- Publisher
- Western Periodicals Co.
- Imprint Place
- North Hollywood, CA
- Imprint Title
- Proceedings of the third annual UMR-MEC conference on energy: energy crisis, an evaluation of our resource potential
- Journal Page Range
- p. 591-601.
Conference
- Title
- 3. annual conference on energy.
- Dates
- 13 Oct 1976.
- Place
- Rolla, MO, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9374281
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; LOFT REACTOR; LOSS OF COOLANT; SIMULATION; SPECIFICATIONS
- Descriptors DEC
- ACCIDENTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:See CONF-761038--.