Published 1977 | Version v1
Book

Loss-of-Fluid Test (LOFT) facility

  • 1. Nuclear Regulatory Commission, Washington, DC

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--.