Published 1984
| Version v1
Book
A TRAC-PF1 analysis of LOFT steam-generator feedwater
Description
The Transient Reactor Analysis Code (TRAC-PF1) calculations were compared to test data from Loss-of-Fluid Test (LOFT) L9-1, which was a loss-of-feedwater transient. This paper includes descriptions of the test and the TRAC input and compares the TRAC-calculated results with the test data. The authors conclude that the code predicted the experiment well, given the uncertainties in the boundary conditions. The analysis indicates the need to model all the flow paths and heat structures, and to improve the TRAC wall condensation heat-transfer model
Additional details
Publishing Information
- Publisher
- Plenum Press.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Anticipated and abnormal plant transients in light water reactors, Vol. 1
- Journal Page Range
- p. 467-475.
Conference
- Title
- Anticipated and abnormal plant transients in light water reactors conference.
- Dates
- 26-29 Sep 1983.
- Place
- Jackson, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16068566
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; FEEDWATER; FLOW MODELS; HEAT TRANSFER; LOFT REACTOR; LOSS OF COOLANT; STEAM GENERATORS; T CODES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS