Published April 2000 | Version v1
Miscellaneous Open

Analysis of modes of heat transfer by fuel damaged by breaking a functioning sidebar of a water-cooled reactor

  • 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)

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Part of:
International Youth Nuclear Congress 2000: Youth, Future, Nuclear. Transactions

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)

Optional Information