Published 1980 | Version v1
Report

Condensation heat transfer coefficients in LWR-containments during LOCA

  • 1. GKSS-Forschungszentrum Geesthacht-Tesperhude, Germany

Description

Best estimate calculations in nuclear safety analysis require replacement of conservative assumptions by measured data or verified correlations. In the field of containment response analysis this holds for condensation heat transfer coefficients at containment structures. In a large scale pressure suppression test facility heat transfer coefficients are determined at structures of the drywell in order to get data representative for break compartments of LWR-containments. Experimental results show heat transfer coefficients of the order 104 W.m-2.K-1 even at presence of noncondensable gas

Additional details

Publishing Information

Imprint Title
Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: PWR and BWR reactor-plant performance analysis and containment technology
Journal Page Range
p. 400-415.
Report number
NUREG/CP--0014(Vol.1)

Conference

Title
ANS/ASME topical meeting on reactor thermal-hydraulics.
Dates
9 - 12 Oct 1980.
Place
Saratoga, NY, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12641480
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONTAINMENT SYSTEMS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE SUPPRESSION; PWR TYPE REACTORS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; CONTAINMENT; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS