Published 1977
| Version v1
Book
1/5-scale experiment of a Mark I boiling-water reactor pressure-suppression system under hypothetical LOCA conditions
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