Published February 1985
| Version v1
Report
RETRAN analysis of ROSA-III small LOCA experiment
Description
In this paper the capability of the RETRAN-02 Code for analysis of BWR small break loss of coolant accidents is discussed. The Rosa-III Test Facility Run 912 experiment, simulation of a BWR 5% break for Japan Atomic Energy Research Institute is described, and results are compared with those of the RETRAN simulation. It is concluded that the RETRAN Code can simulate most of the thermal-hydraulics and fuel temperature behavior, but specific problems are noted
Additional details
Publishing Information
- Imprint Title
- Third international RETRAN conference: proceedings
- Journal Page Range
- p. 35.1-35.20.
- Report number
- EPRI-NP--3803-SR
Conference
- Title
- 3. international RETRAN meeting.
- Dates
- 9-11 Apr 1984.
- Place
- Las Vegas, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023509
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; ECCS; EVALUATED DATA; EXPERIMENTAL DATA; FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; JAERI; LOSS OF COOLANT; R CODES; REACTOR CORES; REACTOR SAFETY; TESTING; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS