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

Part of:
Proceedings of the KNS spring meeting

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