Published 1984
| Version v1
Book
Analysis of core physics and thermal-hydraulics results of control rod withdrawal experiments in the LOFT facility
- 1. EG and G Idaho Inc. P.O. Box 1625, Idaho Falls, ID 83415
Description
Two anticipated transient experiments simulating an uncontrolled control rod withdrawal event in a pressurized water reactor (PWR) were conducted in the Loss-of-Fluid Test (LOFT) Facility at the Idaho National Engineering Laboratory. The scaled LOFT 50-MW(t) PWR includes most of the principal features of larger commercial PWRs. The experiments tested the ability of reactor analysis codes to accurately calculate core reactor physics and thermal-hydraulic phenomena in an integral reactor system
Additional details
Publishing Information
- Publisher
- Elsevier.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Multi-Phase flow and heat transfer III. Part B: Applications
- Journal Page Range
- p. 81-96.
Conference
- Title
- 3. multi-phase flow and heat transfer symposium.
- Dates
- 18-20 Apr 1983.
- Place
- Miami, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17045083
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPUTER CODES; HYDRAULICS; IDAHO NATIONAL ENGINEERING LAB; LOFT REACTOR; REACTOR CORES; ROD DROP ACCIDENTS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS