Published June 2016
| Version v1
Journal article
Simulation of research loop LOBI-MOD2 with RELAP5/MOD3.3 code for LOBI thermo hydraulic test A1-93
Creators
- 1. Islamic Azad Univ., Shiraz (Iran, Islamic Republic of). Dept. of Electrical Engineering
Description
RELAP5/MOD3.3 is one of the used computer codes for the simulation of event thermal-hydraulics of nuclear power plants. The LOBI test facility is a full-power high-pressure integral system test facility, representing an approximately 1: 700 scale model of a 4-loop, 1300 MWe PWR. A new simulation of the small break LOCA test A1-93 has been carried out in a LOBI/Mod2 facility for reaching good agreement and to evaluate the performance of the RELAP5/MOD3.3 code. Good agreement was obtained in general between the code predictions and the experimental data in transient state.
Additional details
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 61
- Journal Issue
- 6
- Journal Page Range
- p. 411-415
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 47087695
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FORECASTING; LOSS OF COOLANT; MASS TRANSFER; NUCLEAR POWER PLANTS; PERFORMANCE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REACTOR OPERATION; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS