Full-scale Mark II CRT Program data report No. 4 (TEST 1101)
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 1977 to provide a data base for evaluation of the LOCA hydrodynamic loads for the Mark II pressure suppression system. The test facility is 1/18 in volume and has a wetwell which is a full-scale replica of one 200-sector of that of a reference Mark II. TEST 1101 is a large (200 mm) water break test performed on March 30, 1979. The test conditions were similar to those for TEST 0004 performed on February 28, 1979, except for small alterations in pool initial temperature and depth. Though the test was performed for a supernominal break area (approx. 160% of the scaled break area for a postulated double-ended break in the recirculation line), the obtained drywell initial pressurization rate (155 kPa/s) was smaller than the safety analysis value for the reference Mark II. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
12585830.pdf
Files
(3.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 116 p.
- Report number
- JAERI-M--8763
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 12585830
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CONTAINMENT SYSTEMS EXPERIMENT; EXPERIMENTAL DATA; HYDRODYNAMICS; LOSS OF COOLANT; MEDIUM PRESSURE; MEDIUM TEMPERATURE; PRESSURE SUPPRESSION; RELIABILITY; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; DATA; FLUID MECHANICS; INFORMATION; MECHANICS; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS