Published 1980 | Version v1
Journal article Metadata-only

Forced convective post-CHF heat transfer and quenching

Creators

  • 1. Edgerton, Germeshausen and Grier Inc, Idaho Falls, Idaho

Description

This paper discusses mechanisms in the postcritical heat flux region that provide understanding and qualitative prediction capability for several current forced-convective heat transfer problems. In the area of nuclear reactor safety, the mechanisms are important in the prediction of fuel rod quenches for the reflood phase, blowdown phase, and possibly some operational transients with dryout. Results using the mechanisms to investigate forced-convective quenching are presented. 26 refs

Additional details

Publishing Information

Journal Title
Am. Soc. Mech. Eng., [Pap.]
Journal Issue
80-wa/ht-69
Series
Am. Soc. Mech. Eng., [Pap.].
ISSN
0402-1215

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12627164
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
CRITICAL HEAT FLUX; FORCED CONVECTION; LOSS OF COOLANT; PWR TYPE REACTORS
Descriptors DEC
ACCIDENTS; CONVECTION; ENERGY TRANSFER; HEAT FLUX; HEAT TRANSFER; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS