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)

MF available from INIS under the Report Number.

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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