Abstract
This report reviewed the R and D states of thermal aging embrittlement of cast stainless steel components in PWRs. Cast stainless steel is being widely used in PWRs including primary piping. This material shows the reduction of fracture toughness during operating life due to high temperature. Micromechanisms and kinetics are summarized to improve the materials properties. The reduction of toughness due to thermal embrittlement in domestic reactors are predicted based on each chemical composition until the end of plant life time. Substantial degradation was predicted in some components during plant life time. (Author) 26 refs., 19 figs., 11 tabs.
Lee, Bong Sang;
Hwa, Hong Jun;
Chi, Se Hwan;
Ryu, Woo Seog;
Kuk, Il Hyun
[1]
- Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Citation Formats
Lee, Bong Sang, Hwa, Hong Jun, Chi, Se Hwan, Ryu, Woo Seog, and Kuk, Il Hyun.
Evaluation on thermal aging embrittlement of cast stainless steel components in domestic PWRs.
Korea, Republic of: N. p.,
1994.
Web.
Lee, Bong Sang, Hwa, Hong Jun, Chi, Se Hwan, Ryu, Woo Seog, & Kuk, Il Hyun.
Evaluation on thermal aging embrittlement of cast stainless steel components in domestic PWRs.
Korea, Republic of.
Lee, Bong Sang, Hwa, Hong Jun, Chi, Se Hwan, Ryu, Woo Seog, and Kuk, Il Hyun.
1994.
"Evaluation on thermal aging embrittlement of cast stainless steel components in domestic PWRs."
Korea, Republic of.
@misc{etde_103138,
title = {Evaluation on thermal aging embrittlement of cast stainless steel components in domestic PWRs}
author = {Lee, Bong Sang, Hwa, Hong Jun, Chi, Se Hwan, Ryu, Woo Seog, and Kuk, Il Hyun}
abstractNote = {This report reviewed the R and D states of thermal aging embrittlement of cast stainless steel components in PWRs. Cast stainless steel is being widely used in PWRs including primary piping. This material shows the reduction of fracture toughness during operating life due to high temperature. Micromechanisms and kinetics are summarized to improve the materials properties. The reduction of toughness due to thermal embrittlement in domestic reactors are predicted based on each chemical composition until the end of plant life time. Substantial degradation was predicted in some components during plant life time. (Author) 26 refs., 19 figs., 11 tabs.}
place = {Korea, Republic of}
year = {1994}
month = {Jun}
}
title = {Evaluation on thermal aging embrittlement of cast stainless steel components in domestic PWRs}
author = {Lee, Bong Sang, Hwa, Hong Jun, Chi, Se Hwan, Ryu, Woo Seog, and Kuk, Il Hyun}
abstractNote = {This report reviewed the R and D states of thermal aging embrittlement of cast stainless steel components in PWRs. Cast stainless steel is being widely used in PWRs including primary piping. This material shows the reduction of fracture toughness during operating life due to high temperature. Micromechanisms and kinetics are summarized to improve the materials properties. The reduction of toughness due to thermal embrittlement in domestic reactors are predicted based on each chemical composition until the end of plant life time. Substantial degradation was predicted in some components during plant life time. (Author) 26 refs., 19 figs., 11 tabs.}
place = {Korea, Republic of}
year = {1994}
month = {Jun}
}