Experimental verification of the feasibility of crack arresting in the WWER-440 reactor pressure vessel material
Description
Three cross-shaped specimens were subjected to testing in conditions simulating a pressurized thermal shock. Out-of-plane stress was present in addition to opening stress. The specimen contained a fatigue cyclized crack and relieving cracks serving to achieve uniform stress intensity factor patterns along the crack front. The specimens were stressed by 8-point bending. The experiments gave evidence that the possibility of arresting the unstable crack propagation also exists in the isothermal experiment with biaxially loaded cross specimens, and that the fracture toughness values of the 15Kh2MFA steel in the arrested crack condition exhibit a rather small dispersion: the lower estimate at temperatures about -70 deg C is about 30 MPa.m-0.5, which is a reasonable value, consistent with the results of other tests performed on standard test specimens as specified by ASTM. (P.A.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Experimentalni overeni moznosti zastaveni trhliny v materialu TNR VVER 440
Publishing Information
- Imprint Pagination
- [29 p.]
- Report number
- UJV--11055-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 31027959
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; DESTRUCTIVE TESTING; FRACTURE PROPERTIES; MECHANICAL PROPERTIES; PRESSURE VESSELS; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 figs., 2 refs.