Mark I 1/5-scale boiling water reactor pressure suppression experiment quick-look report, for test numbers 3. 3(a), 3. 3(b), 3. 4(a), and 3. 4(b) performed on May 3, 1977

Technical Report · Wed Jun 22 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/7212037· OSTI ID:7212037

Lai, W.; Collins, E. K. ^[1]

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1. comps.

The tests conducted on the 1/5-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed here were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90/sup 0/ sector of a 360/sup 0/ torus structure.

• Research Organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 7212037
• Report Number(s): UCID-17446-6; TRN: 77-013826
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
PRESSURE SUPPRESSION
PERFORMANCE TESTING
CONTAINMENT SYSTEMS
MOCKUP
PRESSURE GRADIENTS
ACCIDENTS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTORS
STRUCTURAL MODELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled