Published 1997
| Version v1
Miscellaneous
Loss of coolant accident research for PRC-2 Triga reactor
Description
The author presents the characteristics of the PRC-2 TRIGA reactor, Loss of Coolant Accident (LOCA) analysis code (MCRLOCA code) and True Core Uncovered Model (TCUM). The main calculation schemes of LOCA research, calculation results, sensitivity analysis, safety evaluation and design improvement are also given
Additional details
Publishing Information
- Imprint Title
- Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
- Imprint Pagination
- 1493 p.
- Journal Page Range
- p. O8.1-O8.5
Conference
- Title
- 5. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 14-18 Apr 1997
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29048840
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CHINA; DESIGN; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; MODIFICATIONS; REACTOR CORES; SAFETY ANALYSIS; TRANSIENTS; TRIGA TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ASIA; COMPUTER CODES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS