Published May 2009 | Version v1
Miscellaneous Metadata-only

Characterization of Factors Affecting IASCC of Stainless Steels for Core Internals in PWR

Creators

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Stress corrosion cracking (SCC) of reactor core internals resulting from the material degradation and the water chemistry change due to irradiation has been reported in a fuel rod in 1960's, a control rod in 1970's and a baffle former bolt in recent years of light water reactors (LWR). Under the circumstances, a lot of works have been performed on this irradiation-assisted SCC (IASCC) in boiling water reactors (BWR). Recent efforts have also been focused on IASCC in pressurized water reactors (PWR), but the mechanism in PWR is not fully understood yet as compared with that in BWR due to a lack of data from laboratories and fields. Therefore it is strongly needed to review and analyze recent researches of IASCC in PWR as well as BWR for establishing a proactive management technology for IASCC of core internals in Korean PWR

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2009 spring meeting of the KNS
Dates
18-23 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40101266
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; CONTROL ELEMENTS; CRACKING; FUEL RODS; PWR TYPE REACTORS; REACTOR CORES; STAINLESS STEELS; STRESS CORROSION; WATER CHEMISTRY
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CORROSION; DECOMPOSITION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTORS; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs, 3 figs