Published December 1994
| Version v1
Report
Calculation of the conditions of crack initiation and arrest during a pressurized thermal shock in the material of the WWER-440 reactor pressure vessel
Description
The initiation and arrest of a semi-elliptical surface crack in the WWER-440 reactor pressure vessel was treated. The stress from the pressurized thermal shock was determined by finite element calculations. The code was written in the C computer language. No arrest of the initiated crack was achieved for the various crack axis ratios and transient temperatures applied; there are two apparent reasons for this, viz., that the thermal shock failed to be strong enough, and that there is a rather large difference between fracture toughness KIC and KIA, the fracture toughness characterizing the material resistance against a running crack. (P.A.). 2 figs., 5 refs
Availability note (English)
Available from Ustav jaderneho vyzkumu Rez a.s., 250 68 Rez, Czech Republic.Additional details
Additional titles
- Original title (Czech)
- Vypoctove stanoveni podminek iniciace a zastaveni trhliny pri tlakove-teplotnim soku v materialu tlakove nadoby reaktoru VVER 440
Publishing Information
- Imprint Pagination
- [10 p.].
- Report number
- UJV--10361-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 28001916
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; CRACK PROPAGATION; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; PRESSURE VESSELS; THERMAL SHOCK; TRANSITION TEMPERATURE; WWER TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS