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

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