Published December 1989
| Version v1
Journal article
Effect of the continuous action of the medium on fatigue cracking of nuclear power plant components
Creators
Description
The life of a reactor presssure vessel is most of all limited by slow propagation of subcritical defects up to the critical size. Frequency, load changing, loading wave shape, material variables and water chemistry are the basic factors influencing the rate of growth of the fatigue crack. Recently, substantial knowledge has been achieved of the factors influencing crack growth. (author). 22 figs., 20 refs
Additional details
Additional titles
- Original title (Czech)
- Vliv spojiteho pusobeni prostredi na unavove porusovani komponent jadernych elektraren
Publishing Information
- Journal Title
- Jaderna Energie
- Journal Volume
- 35
- Journal Issue
- 12
- Series
- Jad. Energ.
- Journal Page Range
- 447-455
- ISSN
- 0448-116X
- CODEN
- JADEA
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Serbia and Montenegro
- INIS RN
- 21040400
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CORROSION FATIGUE; CRACK PROPAGATION; CRACKS; DEFECTS; FRACTURE MECHANICS; LIFETIME; LOW ALLOY STEELS; MECHANICAL VIBRATIONS; MILLI HZ RANGE; PRESSURE VESSELS; PWR TYPE REACTORS; REVIEWS; STRESS INTENSITY FACTORS; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; FATIGUE; FREQUENCY RANGE; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT
Optional Information
- Notes
- English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia at US$ 10 per page.