Full-Scale Mark II CRT Program data report, 1
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The Full-Scale Mark II CRT (Containment Response Test) Program was initiated in April 1976 to provide a full-scale data basis for the evaluation of the pressure suppression pool hydrodynamic loads associated with a hypothetical LOCA in a BWR Mark II Containment. The test facility, completed in March 1979, is 1/18 in volume of a typical 1100 MWe Mark II, and has a wetwell which is a full-scale replica of one 200-sector of that of the reference Mark II. The present report documents experimental data from TEST 0002, a medium size (100 mm) water blowdown test, performed by Hitachi Ltd. for JAERI as the second of the four shakedown tests. Test data is provided for the vessel depressurization, the pressure and temperature responses in the test containment, and especially for the chugging phenomena associated with low flux steam condensation in the pool. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
11571372.pdf
Files
(3.5 MB)
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Additional details
Additional titles
- Subtitle (English)
- (TEST 0002)
Publishing Information
- Imprint Pagination
- 104 p.
- Report number
- JAERI-M--8598
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11571372
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SPRAY SYSTEMS; CONTAINMENT SYSTEMS; CONTAINMENT SYSTEMS EXPERIMENT; EXPERIMENTAL DATA; HYDRAULICS; LOSS OF COOLANT; PRESSURE DEPENDENCE; PRESSURE SUPPRESSION; TEMPERATURE DEPENDENCE; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; DATA; INFORMATION; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS