Published February 1987
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Structural analysis of a Japanese BWR MARK-I containment under internal pressure loading
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
As one of the severe accident research programs, elastic-plastic structural analysis concerning the MARK-I steel containment was carried out using the general purpose finite element code ADINA. The analysis revealed that the containment vessel began to yield at the nuckle at 1.70 MPa and that it began to contact at the cylindrical part with the biological shield wall at 1.98 MPa. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
18076876.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 94 p.
- Report number
- JAERI-M--87-003
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18076876
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; BIOLOGICAL SHIELDS; BWR TYPE REACTORS; CONTAINMENT SHELLS; DEFORMATION; ELASTICITY; FINITE ELEMENT METHOD; MECHANICAL STRUCTURES; PLASTICITY; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SHIELDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS