Published June 1990
| Version v1
Journal article
Small break LOCA experiments and verification of CANAC-II code
- 1. Mitsubishi Heavy Industries Ltd., Takasago (Japan). Takasago Research and Development Center
Description
Scaled experiments on small break, loss-of-coolant accidents have been conducted. The tests simulated loss-of-coolant accidents (LOCAs) resulting from a 0.53% and a 0.13% communicative break in the cold leg and the pressurizer power operated relief valve (PORV). The thermal-hydraulic behavior such as natural circulation and reflux condensation cooling during a small break LOCA has been investigated. A new computer program CANAC-II (a Computer Analysis Program of Natural Circulation for multi-loop systems) has been developed and verified based upon comprehensive tests. A drift flux model was applied for two-phase flow in CANAC-II. It also has a shorter computer running time than the real time. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 120
- Journal Issue
- 2/3
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 259-269
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 21080151
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; BLOWDOWN; DIAGRAMS; FLOW RATE; HEAT TRANSFER; L CODES; LOSS OF COOLANT; NATURAL CONVECTION; ONE-DIMENSIONAL CALCULATIONS; PRESSURIZERS; PWR TYPE REACTORS; RUPTURES; SIMULATION; TWO-PHASE FLOW; VALVES; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL EQUIPMENT; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FAILURES; FLOW REGULATORS; FLUID FLOW; INFORMATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS