Published December 1979
| Version v1
Journal article
TRAC analysis of loss-of-fluid test non-nuclear test L1-4
Description
The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos Scientific Laboratory as an advanced best-estimate computer program for analyses of postulated accidents in light water reactors. As a part of the TRAC verification effort, a posttest analysis of loss-of-fluid test (LOFT) non-nuclear test L1-4 has been conducted. The results of this analysis show that TRAC accurately predicts the thermal-hydraulic response of the entire LOFT system, including the delayed effects from emergency core coolant injection into the cold leg
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 46
- Journal Issue
- 3
- Series
- Nucl. Technol.
- Journal Page Range
- 411-421
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11531416
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; ECCS; HEAT TRANSFER; HYDRAULICS; LOFT REACTOR; LOSS OF COOLANT; SIMULATION; T CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS