Radiation Effects on the Mechanical Properties and Microstructure of Type-304 Stainless Steel

Armijo, J. S.; Low, J. R.; Wolff, U.

doi:10.13182/nt65-a20558

Cited by 26 publications

(2 citation statements)

References 7 publications

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“…As with other forms of SCC, early observations suggested that a growing incidence with time and neutron fluence should be expected. IASCC was first reported in the early 1960s 7,8,[15][16][17][18][19][20][21][22][25][26][27][28][29][30][31][32][33][34][35][36] and involved intergranular cracking of stainless steel fuel cladding, with the initiation of multiple cracks occurring from the water side. By contrast, mostly ductile, transgranular cracking was observed in postirradiation mechanical tests performed in inert environments at various strain rates and temperatures.…”

Section: Service Experiencementioning

confidence: 99%

Irradiation Assisted Stress Corrosion Cracking

Andresen

Was

2012

Comprehensive Nuclear Materials

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Section: Service Experiencementioning

confidence: 99%

Irradiation Assisted Stress Corrosion Cracking

Andresen

Was

2012

Comprehensive Nuclear Materials

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“…Subsequent observation made this clearer e.g., by showing a similar effect of the water purity (as measured solution conductivity) on unirradiated and irradiated stainless steel (Figure 4 ). The initial reports of IASCC occurred in the early 1960s (Andresen & Ford, 1995;Andresen, Ford, Murphy, & Perks, 1990a;Armijo, Low, & Wolff, 1965;Brown, Storhok, & Gates, 1967;Bruemmer et al, 1999;Cheng, 1964Cheng, , 1970Cheng, , 1975Cowan & Gordon, 1977;Duncan et al, 1965;Hanninen & Aho-Mantila, 1988;Jacobs & Wozadlo, 1985;Multer, 1975;Pashos et al, 1964;Pasupathi & Klingensmith, 1981;Schaffer, 1962;Scott, 1994;Storrer & Locke, 1970;Was & Andresen, 1992a;2007) and involved intergranular cracking of stainless steel fuel cladding initiating from the water side. Post-irradiation mechanical tests, by comparison, were performed in inert environments at various strain rates and temperatures and exhibited mostly ductile, transgranular cracking.…”

Section: Plant Data On Iasccmentioning

confidence: 99%

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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