Published 1995
| Version v1
Miscellaneous
Critical heat flux calculations for the pressurized water reactors with hexagonal core geometry
Creators
- 1. Institute for Nuclear Research and Nuclear Energy, Sofia (Bulgaria)
- 2. Ship Research Institute, Mitaka, Tokyo (Japan)
Description
Additional correlations for critical heat flux calculations were set up in the modified code COBRA-3C. The agreement between calculated by this code and experimental data base of 584 points proved the correctness of the modifications. Proposal for critical heat-flux prediction by using Bezrukov and Smolin 1978 was made. The subchannel steady-state and accident analyses of Kozloduy Nuclear Power Plant pointed out the conservative design of VVER-440. The using of modified code and performing of specific calculations for nuclear power plants with VVER is aimed to improve the quality of their safety analyses. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 1
- Imprint Pagination
- 701 p.
- Journal Page Range
- p. 553-558
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38007345
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; HEXAGONAL CONFIGURATION; NUMERICAL ANALYSIS; PWR TYPE REACTORS; REACTOR LATTICES; TRANSIENTS; TRIANGULAR CONFIGURATION; VALIDATION
- Descriptors DEC
- CONFIGURATION; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT FLUX; MATHEMATICS; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs., 10 figs., 5 tabs.