Published 1976
| Version v1
Report
Determination of the safety of conditions. A1 pressure vessel
Creators
Description
The possibilities of origination of brittle fracture in the reactor pressure vessel of the first Czechoslovak Nuclear Power Station were studied. Crack arrest temperature criterion and the critical size of flaw were evaluated and changes in the material properties during the reactor operation were determined
Additional details
Publishing Information
- Imprint Title
- Fracture mechanics applications: Implications of detected flaws
- Journal Page Range
- p. 243-248.
- Report number
- IAEA--189
Conference
- Title
- Implications of detected flaws.
- Acronym
- Specialists' meeting on fracture mechanics applications
- Dates
- 3 - 5 Dec 1975.
- Place
- Winterthur, Switzerland.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 9360803
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRITTLENESS; DEFECTS; MATERIALS TESTING; PRESSURE VESSELS; RADIATION EFFECTS
- Descriptors DEC
- CONTAINERS; MECHANICAL PROPERTIES; TESTING