Published 1979
| Version v1
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Reliability and safety of nuclear power stations
Description
The main problems are briefly discussed associated with the assessment of the safety and reliability of reactor pressure vessels. Two approaches are being applied to the assessment: one is based on the crack arrest temperature, the other on the determination of conditions corresponding to brittle fracture formation and on the determination of the critical defect size. The importance is stressed of continuous in-service inspection which may increase the factor of reliability by up to 104 times. (Z.M.)
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- ZJE--233
INIS
- Country of Publication
- Serbia and Montenegro
- Country of Input or Organization
- Serbia and Montenegro
- INIS RN
- 12596568
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAILURES; IN-SERVICE INSPECTION; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY; SAFETY ANALYSIS
- Descriptors DEC
- CONTAINERS; INSPECTION; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS