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Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels

Abstract

Austenitic stainless steels are widely used as structural components in reactor pressure vessel internals because of their high strength, ductility, and fracture toughness. However, exposure to neutron irradiation results in changes in microstructure, mechanical properties and microchemistry of the steels. Irradiation assisted stress corrosion cracking (IASCC) caused by the effect of neutron irradiation during long term plant operation in high temperature water environments is considered to take the form of intergranular stress corrosion cracking (IGSCC) and the critical fluence level has been reported to be about 5x10{sup 24}n/m{sup 2} (E>1MeV) in Type 304 stainless steel in BWR environment. JNES had been conducting IASCC project during the JFY (2000) - JFY (2008) period, and prepared an engineering database on IASCC. However, the data of Crack Growth Rate (CGR) below the critical fluence level are not sufficient. So, this project was initiated to obtain the CGR data below the critical fluence level. Test specimens have been irradiated in the Halden reactor, operating by the OECD Halden Reactor Project, and the post irradiation examination (PIE) will be conducted from JFY (2011) to JFY (2013), finally the modified IASCC guide will be prepared in JFY (2013). (author)
Authors:
"NONE"
Publication Date:
Aug 15, 2013
Product Type:
Technical Report
Report Number:
JNES-RE-2013-0001
Resource Relation:
Other Information: 3 refs., 9 figs., 3 tabs.; Related Information: In: Annual safety research report, JFY 2012| Japan Nuclear Energy Safety Organization, Tokyo (Japan)| 708 p.
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AUSTENITIC STEELS; BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; IRRADIATION; NEUTRONS; SHROUDS; STRESS CORROSION; TUBES
OSTI ID:
22357685
Research Organizations:
Japan Nuclear Energy Safety Organization (JNES), Plant Inspection and Maintenance Evaluation Department, Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
TRN: JP1501599062860
Availability:
Available from the Internet at URL http://www.nsr.go.jp/archive/jnes/content/000125907.pdf
Submitting Site:
INIS
Size:
page(s) 215-221
Announcement Date:
Jul 18, 2015

Citation Formats

Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels. Japan: N. p., 2013. Web.
Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels. Japan.
2013. "Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels." Japan.
@misc{etde_22357685,
title = {Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels}
abstractNote = {Austenitic stainless steels are widely used as structural components in reactor pressure vessel internals because of their high strength, ductility, and fracture toughness. However, exposure to neutron irradiation results in changes in microstructure, mechanical properties and microchemistry of the steels. Irradiation assisted stress corrosion cracking (IASCC) caused by the effect of neutron irradiation during long term plant operation in high temperature water environments is considered to take the form of intergranular stress corrosion cracking (IGSCC) and the critical fluence level has been reported to be about 5x10{sup 24}n/m{sup 2} (E>1MeV) in Type 304 stainless steel in BWR environment. JNES had been conducting IASCC project during the JFY (2000) - JFY (2008) period, and prepared an engineering database on IASCC. However, the data of Crack Growth Rate (CGR) below the critical fluence level are not sufficient. So, this project was initiated to obtain the CGR data below the critical fluence level. Test specimens have been irradiated in the Halden reactor, operating by the OECD Halden Reactor Project, and the post irradiation examination (PIE) will be conducted from JFY (2011) to JFY (2013), finally the modified IASCC guide will be prepared in JFY (2013). (author)}
place = {Japan}
year = {2013}
month = {Aug}
}