Published May 2000
| Version v1
Miscellaneous
Fracture toughness master curve characterization of the low toughness linde 80 weld by small ABI and PCVN specimens
- 1. KAERI, Taejon (Korea, Republic of)
- 2. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Description
Un-irradiated fracture toughness of the Kori-1 RPV Linde 80 weld was characterized by small specimens PCVN and ABI testing in the transition temperature region. The PCVN 3-point bend tests were carried out following the ASTM standard E1921-97 master curve method while the semiempirical IEF (indentation energy to fracture) theory was used for ABI data analysis. The result from the ABI tests was comparable to that of the standard fracture toughness tests. The proposed methodology would be very useful to evaluate irradiation embrittlement of pressure vessel steels with a limited volume of irradiated materials. Some special features of the low toughness weld were also discussed
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [CDROM]
- Journal Page Range
- [8 p.]
Conference
- Title
- 2000 spring meeting of the KNS
- Dates
- 26-27 May 2000
- Place
- Kori (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 34027646
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DATA ANALYSIS; DIAGRAMS; EMBRITTLEMENT; FRACTURE PROPERTIES; FRACTURES; KORI-1 REACTOR; PRESSURE VESSELS; REACTOR VESSELS; STANDARDS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; INFORMATION; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs, 4 figs, 2 tabs