Published 1977 | Version v1
Book

1/5-scale experiment of a Mark I boiling-water reactor pressure-suppression system under hypothetical LOCA conditions

  • 1. Univ. of California, Livermore

Description

Experimental results show the sensitivity of hydrodynamically generated vertical loads to changes in the drywell pressurization rate, downcomer submergence, and vent-line loss coefficient. Insignificant effects on peak vertical loads were observed when the vent-line loss coefficient was varied. Peak vertical loads can be reduced by adding initial drywell overpressure so that the downcomers are partly cleared of water. Spatial variation of pressure at about the time of vent clearing is seen in comparisons of data from locations along the axis of the toroidal wetwell

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL
Imprint Title
Thermal reactor safety. Vol. III
Journal Page Range
p. 683-706.

Conference

Title
Thermal reactor safety meeting.
Dates
31 Jul - 5 Aug 1977.
Place
Sun Valley, ID, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10437502
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONDENSATION CHAMBERS; CONTAINMENT SYSTEMS; HYDRODYNAMICS; LOSS OF COOLANT; PRESSURE SUPPRESSION; SIMULATION; TORI
Descriptors DEC
ACCIDENTS; CONTAINMENT; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS