Effects of neutron irradiation on corrosion and segregation behavior in austenitic stainless steels

Nakahigashi, Shigeo; Kodama, Mutsuo; Fukuya, Koji; Nishimura, Seiji; Yamamoto, Seiji; Saito, Kiyoshi; Saito, Tasuku

doi:10.1016/0022-3115(91)90275-c

Cited by 14 publications

(6 citation statements)

References 2 publications

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“…RIS profi les are also characterized by their narrowness, often confi ned to within Brought to you by | University of Hawaii Main Library Authenticated Download Date | 6/16/15 11:10 PM RIS increases with neutron dose in LWRs and saturates after several ( ∼ 5) dpa in the 300 ° C temperature range. Figure 34 shows grain boundary chromium depletion for austenitic stainless steels as a function of dose (Asano, Fukuya, Nakata, & Kodama, 1992;Carter et al, 1994;Jacobs, 1995;Jacobs, Clausing, Miller, & Shepherd, 1990;Jacobs et al, 1993;Kenik, 1992;Nakahigashi et al, 1992;Walmsley, Spellward, Fisher, & Jenssen, 1997;Was et al, 2002). As the slowest diffusing element, nickel, becomes enriched at the grain boundary.…”

Section: Metallurgy and Microstructurementioning

confidence: 96%

Irradiation-assisted stress corrosion cracking

Was¹,

Ashida²,

Andresen³

2011

Corrosion Reviews

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Irradiation-assisted stress corrosion cracking (IASCC) refers to the process(es) by which irradiation enhances the inherent susceptibility of alloys to stress corrosion cracking (SCC). This article begins with an introduction to the IASCC problem experienced in light water reactors, followed by a summary of existing plant and laboratory data that reveal its dependence on irradiation, environment and alloy parameters. The specifi c effects of irradiation on IASCC are classifi ed into two categories: the effects on water chemistry and the effects on microstructure. Water chemistry effects include radiolysis and its effects on corrosion potential, and effects of corrosion potential on IASCC. Microstructure effects include radiationinduced segregation (RIS), irradiated microstructure, swelling and creep, and hydrogen and helium generation. Leading mechanisms proposed to explain the role of radiation in the SCC process are: radiolysis and crack tip strain rate, grain boundary chromium depletion, irradiation hardening, localized deformation and RIS of minor elements. As nuclear power plants operate for longer, an increased incidence of SCC can be expected unless active mitigation steps are taken. Drawing on the accumulated understanding over the past four decades of the key processes believed to control IASCC, a set of attributes of an ideal, IASCC-resistant alloy are identifi ed as a fi rst step.

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Section: Metallurgy and Microstructurementioning

confidence: 96%

Irradiation-assisted stress corrosion cracking

Was¹,

Ashida²,

Andresen³

2011

Corrosion Reviews

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“…Figure 17 shows grain boundary chromium depletion for austenitic stainless steels as a function of dose. [89][90][91][92][93][94][95][96][97] As the slowest diffusing element, nickel becomes enriched at the grain boundary. Since iron depletes in 304 and 316 stainless steels, the nickel enrichment makes up for both chromium and iron depletion and can reach very high levels up to $30 wt%.…”

Section: Radiation-induced Segregationmentioning

confidence: 99%

“…There is large scatter in the data that makes a direct correlation difficult to support, and differences in testing conditions undoubtedly contribute. 304 (82) 304 (13) 304 (91) 304 (92) 304 (93) 316 (82) 316 (94) 348 (91) HP 304 (95) CP 304 (95) CP 316 (95) CP 304 (17) CP 316 (17) HP 316 (17) CP 304 Among the minor alloy elements, only Si is known to segregate to high levels, and Si segregation is correlated with IASCC. Experiments by Busby et al 107,108 on a high-purity 316 base alloy doped with 1 wt% Si showed severe IASCC in NWC and in primary water after irradiation to 5.5 dpa at 360 C. STEM measurements of grain boundary Si confirm levels up to 6 wt%.…”

Section: Radiation-induced Segregationmentioning

confidence: 99%

Irradiation Assisted Stress Corrosion Cracking

Andresen

Was

2012

Comprehensive Nuclear Materials

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“…1 A large number of studies have reported radiationinduced segregation in LWR-relevant conditions. [2][3][4][5][6][7][8][9][10] At LWR temperatures (290-310C), the depletion of chromium and enrichment of nickel and silicon get larger as a function of irradiation dose, for chromium decreasing from bulk levels (20-24 wt.%) to approximately 12-16 wt.% after about 5-10 dpa. [2][3][4][5][6][7][8][9][10] Silicon enriches at boundaries reaching as high as 10% by 10 dpa.…”

Section: Radiation-induced Segregationmentioning

confidence: 99%

“…[2][3][4][5][6][7][8][9][10] At LWR temperatures (290-310C), the depletion of chromium and enrichment of nickel and silicon get larger as a function of irradiation dose, for chromium decreasing from bulk levels (20-24 wt.%) to approximately 12-16 wt.% after about 5-10 dpa. [2][3][4][5][6][7][8][9][10] Silicon enriches at boundaries reaching as high as 10% by 10 dpa. A damage of 1-10 dpa is the dose range over which irradiation-assisted stress corrosion cracking (IASCC) is first evident in LWR materials, although studies have not provided a definitive connection between grain boundary composition and IASCC susceptibility.…”

Section: Radiation-induced Segregationmentioning

confidence: 99%

Radiation damage concerns for extended light water reactor service

Allen

Busby

2009

JOM

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How would you……describe the overall signifi cance of this paper? To meet growing energy needs along with reduced CO 2 emissions, the long-term safe and economical operation of current nuclear power plants will be required. Radiation damage is a unique aspect of nuclear reactor service and must be carefully examined for different materials and components under extended operation scenarios.…describe this work to a materials science and engineering professional with no experience in your technical specialty? Radiation damage is a unique aspect of nuclear reactor service and can lead to signifi cant changes in materials properties and performance. Extending the operating lifetime of a nuclear reactor will allow for greater energy production, but will also increase neutron exposure. An examination of possible radiation damage effects for extended service is provided in this paper.…describe this work to a layperson? Radiation exposure to nuclear reactor components can lead to changes in materials properties and performance during operation. Understanding and predicting these changes is important in the safe and effi cient operation of nuclear power plants. This paper describes some of the forms of radiation-induced degradation that might occur during the extended operation of a nuclear power plant.

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Effects of neutron irradiation on corrosion and segregation behavior in austenitic stainless steels

Cited by 14 publications

References 2 publications

Irradiation-assisted stress corrosion cracking

Irradiation-assisted stress corrosion cracking

Irradiation Assisted Stress Corrosion Cracking

Radiation damage concerns for extended light water reactor service

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