Experimental and analytical seismic study on 600 MWe CANDU core
Creators
- 1. Electric Power Development Co. Ltd., Tokyo (Japan)
Description
Following the completion of STEP I and II tests, a third and final test (STEP III) of the CANDU core seismic verification program was conducted by EPDC together with a supportive analytical study. The test provided further assurance of shut-off rod insertion capability in addition to information on collision behavior between guide tube and fuel channel assembly. Furthermore it was shown that the seismic response of the CANDU core including collision behavior can be predicted with an acceptable degree of confidence by analytical means. The findings obtained from this comprehensive program led to the conclusion that the CANDU core can maintain its safety function as well as its structural integrity under extemely strong earthquake motion excitation conditions
Additional details
Publishing Information
- Imprint Title
- Second annual conference, 1981
- Imprint Pagination
- 444 p.
- Journal Page Range
- p. 351-357.
- Report number
- INIS-mf--8473
Conference
- Title
- Canadian Nuclear Society 2. annual conference.
- Dates
- 10 Jun 1981.
- Place
- Ottawa, Ontario (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 14769042
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CHANNELS; MECHANICAL TESTS; MECHANICAL VIBRATIONS; P CODES; REACTOR CORES; REACTOR SHUTDOWN; SCRAM RODS; SEISMIC EFFECTS
- Descriptors DEC
- COMPUTER CODES; CONTROL ELEMENTS; HEAVY WATER MODERATED REACTORS; MATERIALS TESTING; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SHUTDOWN; TESTING; THERMAL REACTORS