Published July 1, 1977
| Version v1
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Mark I 1/5-scale boiling water reactor pressure suppression experiment quick-look report for test numbers 2.7, 2.8, 2.9, 2.10, and 2.11 performed on May 12, 1977
Description
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 900 sector of a 3600 torus structure
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.Files
8347790.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 116 p.
- Report number
- UCRL--17446--7
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8347790
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; LOSS OF COOLANT; MOCKUP; PERFORMANCE TESTING; PRESSURE GRADIENTS; PRESSURE SUPPRESSION; STRESSES
- Descriptors DEC
- ACCIDENTS; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS