Published June 1987
| Version v1
Journal article
Calculation of crack size in WWER reactor vessel
Creators
Description
The technique for calculated substantiation of permissible sizes of cladding semielliptical crack in WWER vessel is presented. The most loaded hydrotest regime and violations in the system of boron control are chosen as calculated regimes. The history of vessel cyclic loading and changes of mechanical properties of vessel material in the process of reactor exploitation were taken into account during calculations. The critical crack depth is determined depending on reactor service life. The choice of safety factor coefficient to substantiate permissible crack sizes is suggested. The final permissible crack depth is 9 mm
Additional details
Additional titles
- Original title (Russian)
- Расчёт допустимых размеров трещины в корпусе ВВЭР
Publishing Information
- Journal Title
- At. Ehnerg.
- Journal Volume
- 62
- Journal Issue
- 6
- Series
- At. Ehnerg.
- Journal Page Range
- 379-382
- ISSN
- 0004-7163
- CODEN
- AENGA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 19066429
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CLADDING; CRACK PROPAGATION; DEPTH; FRACTURE PROPERTIES; LOW ALLOY STEELS; NUMERICAL SOLUTION; PERFORMANCE TESTING; PRESSURE VESSELS; S-N DIAGRAM; STRESS INTENSITY FACTORS; TIME DEPENDENCE; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; DEPOSITION; DIAGRAMS; DIMENSIONS; ENRICHED URANIUM REACTORS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STEELS; SURFACE COATING; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS