Analysis of modes of heat transfer by fuel damaged by breaking a functioning sidebar of a water-cooled reactor
Creators
- 1. Russian Federal Nuclear Center, VNIIEF, Mira Avenue 37, 607190 Sarov, Arzamas-16, Nizhny Novgorod Region (Russian Federation)
Description
In the study, a new way to measure the length of film boiling on surfaces of heating particles with reference to the fault condition (interaction of fuel with coolant) in a NPP was considered. Presented is a description of the experimental installation, strategies, and results of length measurements of film boiling of water on spheres of different diameters from honeys and aluminum under different temperatures of interaction. These results can be used to test models and codes for the evaluation of heating efficiency during boiling under corresponding conditions. The primary use of the present work is to verify and calibrate heat transfer correlations us ing the results of experiments. Using correlations to conduct analyses of heat transfer during the boiling on spheres from honeys and aluminum and with provision for results of the experience, boiling curves are produced describing dependency of flow of heat (Q) on fuel temperature (To), size (R), ball material, and temperature of surrounding water (TL). (authors)
Files
32015299.pdf
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Additional details
Publishing Information
- Publisher
- Slovak Nuclear Society
- Imprint Place
- Trnava (Slovakia)
- Imprint Title
- International Youth Nuclear Congress 2000: Youth, Future, Nuclear. Transactions
- Imprint Pagination
- 312 p.
- Journal Page Range
- p. 231
- Report number
- INIS-SK--2001-001
Conference
- Title
- International Youth Nuclear Congress 2000
- Acronym
- IYNC 2000
- Dates
- 9-14 Apr 2000
- Place
- Bratislava (Slovakia)
INIS
- Country of Publication
- Slovakia
- Country of Input or Organization
- Slovakia
- INIS RN
- 32015299
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; FLUID MECHANICS; FLUID-STRUCTURE INTERACTIONS; FUEL ELEMENTS; FUEL-COOLANT INTERACTIONS; FUNCTIONAL MODELS; MATHEMATICAL MODELS; MOLTEN METAL-WATER REACTIONS; NUCLEAR FUELS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SOURCES; ENERGY SYSTEMS; FUELS; MATERIALS; MECHANICS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; SAFETY