Published 1990 | Version v1
Book

Rewetting of hot surfaces-evaluation of wet region heat transfer coefficient from experimental data and prediction of rewetting velocity based on two-region model

  • 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.

Description

The phenomenon of rewetting of hot surfaces is of significance in the context of emergency core cooling of water cooled nuclear reactors. Solutions have been obtained for conduction controlled rewetting of hot surfaces, based on two-region model, and these are correlated to relate Biot number and Peclet number and the non-dimensional temperature. Using these and the published data on rewetting velocity, wet region heat transfer coefficient values have been evaluated separately for falling film rewetting and bottom flooding rewetting. Based on these values correlations have been obtained for the wet region heat transfer coefficient by regression analysis. These correlations along with that for Peclet number have been used for predicting rewetting velocities. Reasonably good agreement is noted between the predicted values and experimental data

Additional details

Publishing Information

Publisher
Hemisphere Publishing.
Imprint Place
New York, NY (USA)
ISBN
0-89116-909-1
Imprint Title
Heat transfer 1990. Proceedings of the ninth international heat transfer conference
Imprint Pagination
460 p.
Journal Page Range
p. 23-28.

Conference

Title
9. international heat transfer conference.
Dates
19-24 Aug 1990.
Place
Jerusalem (Israel).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22051982
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COOLING; ECCS; EXPERIMENTAL DATA; HEAT TRANSFER; MATHEMATICAL MODELS; REACTOR SAFETY; SURFACES; THERMODYNAMICS; WATER COOLED REACTORS
Descriptors DEC
DATA; ENERGY TRANSFER; INFORMATION; NUMERICAL DATA; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY

Optional Information

Secondary number(s)
CONF-900803--.