IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing

被引：2

作者：

Hesterberg, Justin R. ^{[1
]}

Jiao, Zhijie ^{[1
]}

Was, Gary S. ^{[1
]}

机构：

[1] Univ Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 USA

来源：

PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2 | 2018年

关键词：

IASCC; Irradiation; Hardening; Dislocation channels; Post-irradiation annealing; Neutron-irradiated; Stainless steel; STRESS-CORROSION CRACKING; RADIATION-INDUCED SEGREGATION; LOCALIZED DEFORMATION; MICROSTRUCTURE; TEMPERATURE;

D O I：

10.1007/978-3-319-68454-3_74

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Post-irradiation annealing (PIA) was conducted to investigate the cause of irradiation-assisted stress corrosion cracking (IASCC). The effects of PIA on irradiation hardening, dislocation channel formation, and IASCC susceptibility were examined for a 304L stainless steel irradiated to 5.9 dpa in the Barseback-1 reactor (Sweden). The annealing treatments were performed at temperatures in the range 450-600 degrees C and times ranging from 1-20 h. Longer annealing times and higher temperatures, as represented by iron diffusion distance, resulted in a significant reduction in irradiation hardening. IASCC susceptibility was measured for the as-irradiated and two PIA conditions (500 degrees C: 1 h and 550 degrees C: 20 h) via interrupted CERT tests under simulated BWR-NWC conditions. The annealing treatments progressively reduced IASCC susceptibility (as measured by the final intergranular fracture fraction) and dislocation channel density.

引用

页码：1015 / 1026

页数：12

共 22 条

[1] Asano K., 1995, 7th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst, P1033
[2] Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels
Busby, JT
Was, GS
Kenik, EA
[J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 302 (01) : 20 - 40
[3] Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel
Chen, Yimeng
Chou, Peter H.
Marquis, Emmanuelle A.
[J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 451 (1-3) : 130 - 136
[4] DEPENDENCE OF RADIATION-INDUCED SEGREGATION ON DOSE, TEMPERATURE AND ALLOY COMPOSITION IN AUSTENITIC ALLOYS
DAMCOTT, DL
ALLEN, TR
WAS, GS
[J]. JOURNAL OF NUCLEAR MATERIALS, 1995, 225 : 97 - 107
[5] Influence of localized deformation on A-286 austenitic stainless steel stress corrosion cracking in PWR primary water
Fournier, L.
Savoie, M.
Delafosse, D.
[J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 366 (1-2) : 187 - 197
[6] Separation of microstructural and microchemical effects in irradiation assisted stress corrosion cracking using post-irradiation annealing
Fukuya, K
Nakano, M
Fujii, K
Torimaru, T
Kitsunai, Y
[J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (12) : 1218 - 1227
[7] Current understanding of radiation-induced degradation in light water reactor structural materials
Fukuya, Koji
[J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2013, 50 (03) : 213 - 254
[8] LOW-TEMPERATURE ANNEALING - A PROCESS TO MITIGATE IRRADIATION-ASSISTED STRESS-CORROSION CRACKING
JACOBS, AJ
WOZADLO, GP
GORDON, GM
[J]. CORROSION, 1995, 51 (10) : 731 - 737
[9] Impact of localized deformation on IASCC in austenitic stainless steels
Jiao, Z.
Was, G. S.
[J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 408 (03) : 246 - 256
[10] The role of irradiated microstructure in the localized deformation of austenitic stainless steels
Jiao, Z.
Was, G. S.
[J]. JOURNAL OF NUCLEAR MATERIALS, 2010, 407 (01) : 34 - 43

← 1 2 3 →