Published January 1976
| Version v1
Report
Restricted
Probabilistic assessment of primary piping integrity
Description
The structural reliability assessment of the Clinch River Breeder Reactor primary cold leg piping is discussed
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-760622--40
Conference
- Title
- American Nuclear Society 1976 annual meeting.
- Dates
- 13 Jun 1976.
- Place
- Toronto, Ontario, Canada.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8284229
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; FAILURES; PRIMARY COOLANT CIRCUITS; RELIABILITY; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SODIUM COOLED REACTORS; SYSTEMS ANALYSIS
Optional Information
- Notes
- Available from NTIS. $3.50.