Comparison of experimental results with RETRAN calculations of LOFT experiment L3-1
Description
This paper discusses comparisons between pretest predictions performed for Loss-of-Fluid Test (LOFT) Loss-of-Coolant Experiment (LOCE) L3-1 using preliminary versions of RETRAN-02. This project was sponsored by the Electric Power Research Institute to assess the applicability of the loss-of-fluid test (LOFT) experimental test results to large pressurized water reactor behavior during postulatd accidents and to validate the abiity of thermal hydraulic codes such as RETRAN to describe accurately reactor behavior during apostulated loss-of-coolant accident (LOCA). An integral part of this project was an evaluation of the adequacey of the LOFT data. The LOFT data were reviewed from the viewpoints of understanding the accident behavior of pressurized water reactors (PWRs) and to evaluate the consistency, accuracy, and completeness of the experimental data for code assessment purposes
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Title
- Conference proceedings: first international RETRAN conference
- Journal Page Range
- p. 7.1-7.15.
- Report number
- EPRI-WS--80-150
Conference
- Title
- 1. international RETRAN conference.
- Dates
- 22 - 24 Sep 1980.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12624847
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; LOFT REACTOR; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE GRADIENTS; REACTOR SAFETY; SIMULATION; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS