Published August 1977
| Version v1
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Behavior of zircaloy cladding under a postulated loss-of-coolant accident condition
Description
This report is a review of studies on the behavior of zircaloy cladding under a postulated loss-of-coolant accident condition. Experimental data of zircaloy-steam reaction rate, embrittlement of a steam-oxidized zircaloy and cladding deformation are summarized. Sensitivity studies of various parameters on LOCA analysis by a computer code are presented. (auth.)
Availability note (English)
MF available from INIS under the Report Number.Files
9379630.pdf
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Additional details
Additional titles
- Subtitle (English)
- A report of the working group on review of the behavior of fuel cladding under a loss-of-coolant accident
Publishing Information
- Imprint Pagination
- 101 p.
- Report number
- JAERI-M--7247
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 9379630
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; DEFORMATION; EMBRITTLEMENT; FUEL CANS; LOSS OF COOLANT; OXIDATION; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR SAFETY; REVIEWS; STEAM; SWELLING; TEMPERATURE DEPENDENCE; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; DOCUMENT TYPES; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTORS; SAFETY; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS