Published March 1973
| Version v1
Report
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Growth considerations for large hypothetical cracks in nuclear reactor coolant piping
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- CENPD--89
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4081052
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANALYTICAL SOLUTION; CRACKS; ELASTICITY; FAILURES; FRACTURE PROPERTIES; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS
- Descriptors DEC
- MECHANICAL PROPERTIES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TENSILE PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS