Published 2004
| Version v1
Journal article
RELAP 5 - A possibility for CANDU 6 safety analysis evaluation
Creators
- 1. 'Politehnica' University of Bucharest, Splaiul Independentei 313, Sector 6, R-77206 Bucharest (Romania)
Description
Usually, the CATHENA code is used for the safety analysis of CANDU reactors. However, assessment of RELAP 5 code versus experimental results was done and the auditing analysis for CANDU reactors was performed mainly in Korea. This paper briefly describes the capability of RELAP 5 code for the analysis of transient regimes in water cooled reactors and presents an application of this code for core flow blockage accident in a CANDU reactor. (author)
Additional details
Additional titles
- Original title (Romanian)
- RELAP 5 - posibilitate de verificare a analizelor de securitate pentru CANDU 6
Publishing Information
- Journal Title
- Energia Nucleara
- Journal Volume
- 16
- Journal Issue
- 1-2
- Journal Page Range
- p. 33-34
- ISSN
- 1220-5508
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 35073378
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- C CODES; CANDU TYPE REACTORS; COOLANTS; FLOW BLOCKAGE; R CODES; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; REPUBLIC OF KOREA; RISK ASSESSMENT; SAFETY ANALYSIS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACCIDENTS; ASIA; COMPUTER CODES; DEVELOPING COUNTRIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS
Optional Information
- Notes
- 5 refs., 3 figs.