Published 1982
| Version v1
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Thermal and hydrodynamic analysis of the refueling stand pipe under normal and accidental conditions
Description
The effect of natural convection on the gas temperature distribution inside the refueling stand pipe for the experimental VHTR is investigated numerically. The analysis is carried out using a computer program which solves continuity, momentum, and energy equations in finite difference form. The results show: (1) The gas temperature exceeds the limiting value of the internal structure when the lower region of the stand pipe is not thermally insulated. (2) The gas temperature can be maintained below the limiting value under both normal and accidental conditions when the lower region is thermally insulated
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Additional details
Publishing Information
- Imprint Title
- Third Japan-US seminar on HTGR safety technology: proceedings. Volume I
- Journal Page Range
- p. 231-239.
- Report number
- NUREG/CP--0045-Vol.1
Conference
- Title
- 3. Japan/US HTGR safety technology seminar.
- Dates
- 2-3 Jun 1982.
- Place
- Upton, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15034071
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONTROL ROD DRIVES; DIFFERENTIAL EQUATIONS; EQUIPMENT PROTECTION DEVICES; HEAT TRANSFER; HYDRAULICS; JAERI; MATHEMATICAL MODELS; NATURAL CONVECTION; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR VESSELS; TEMPERATURE DISTRIBUTION; THERMAL INSULATION; VHTR REACTOR
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; JAPANESE ORGANIZATIONS; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS