Published June 2000
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Natural convection as the way of heat removal from fast reactor core at cooldown regimes
- 1. State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)
Description
The problems of thermohydraulics in fast reactors at cooldown regimes at heat removal by natural convection are considered The results of experiments and calculations obtained in various countries in this area are presented. The special attention is given to heat removal through inter-assembly space in the core and also to problems of thermohydraulics in the upper plenum. (author)
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Additional details
Publishing Information
- Imprint Title
- LMFR core thermohydraulics: Status and prospects
- Imprint Pagination
- 443 p.
- Journal Page Range
- p. 403-434
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1157
Conference
- Title
- Technical committee meeting on methods and codes for calculations of thermohydraulic parameters for fuel, absorber pins and assemblies of LMFR's with traditional and burner cores
- Dates
- 27-31 Jul 1998
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31032893
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CALCULATION METHODS; FAST REACTORS; FUEL ASSEMBLIES; HYDRODYNAMICS; NATURAL CONVECTION; REACTOR CORES; THERMAL ANALYSIS
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FLUID MECHANICS; HEAT TRANSFER; MASS TRANSFER; MECHANICS; REACTOR COMPONENTS; REACTORS; REMOVAL
Optional Information
- Notes
- 46 refs, 25 figs, 3 tabs