Stress corrosion cracking on irradiated 316 stainless steel

Furutani, Gen; Nakajima, Nobuo; Konishi, Takao; Kodama, Mutsuo

doi:10.1016/s0022-3115(00)00704-2

Cited by 34 publications

(14 citation statements)

References 6 publications

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“…In addition to these two factors of in-situ irradiation and fatigue loading, structural materials are also exposed to hydrogen isotopes due to nuclear transmutation and permeation from light-water coolants in the reactor core environment. Although the important role of hydrogen in irradiated assisted corrosion cracking (IASCC) has been suggested in some literature, 4,5) the effects of hydrogen isotopes on material behaviors under in-situ irradiation have been little examined due to some technological difficulties to establish in-situ irradiation testing facilities.…”

Section: Introductionsupporting

confidence: 84%

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C

Murase¹,

Yamamoto

2011

Mater. Trans.

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Stress-controlled fatigue tests were performed for 20% cold-worked 316 stainless steel under in-situ 10 MeV deuteron irradiation with an energy degrader at 60 and 300 C. The irradiation dose rate and the deuterium implantation rate were arranged in response to beam intensity in three conditions as (A) 1:0 Â 10 À7 dpa/s and 1:1 Â 10 À3 appm/s, (B) 5:0 Â 10 À7 dpa/s and 5:5 Â 10 À3 appm/s and (C) 1:0 Â 10 À6 dpa/s and 1:1 Â 10 À2 appm/s, respectively. The number of fatigue cycles to fracture (N F ) increased with the dose rate in order of conditions (A), (B) and (C) at 300 C, while N F was lower in condition (C) than that in condition (B) irrespective of the higher dose rate at 60 C. Although transgranular cracking in the ductile fracture mode was indicated on fracture surface for all specimens, higher density of dimples was formed for the in-situ irradiation specimen in condition (C) at 60 C. Some evidence of effects of implanted deuterium on in-situ irradiation fatigue behavior were demonstrated in this paper.

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Section: Introductionsupporting

confidence: 84%

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C

Murase¹,

Yamamoto

2011

Mater. Trans.

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“…16) The same 35-dpa materials fractured in a fully ductile manner in conventional tensile tests at 320 C at a strain rate of 1 Â 10 À4 /s. 14,17) The present results showed that no grain boundary separation occurred in the 35-dpa specimen under the same conditions as the previous tensile tests, at least when deformed to 0.5% plastic strain. The mechanism of Fig.…”

Section: Grain Boundary Separationmentioning

confidence: 99%

“…It is well known from SSRT tests that IASCC susceptibility in simulated PWR primary water estimated by the intergranular fraction in the fracture surface increases with neutron fluence, water temperature and dissolved hydrogen (DH) concentration. 14,17,[19][20][21] Some data showed that IASCC initiation occurred at a stress below the as-irradiated yield strength, as low as 400-500 MPa. A higher DH concentration resulted in a lower maximum stress, suggesting the influence of DH on IASCC initiation.…”

Section: Relation To Iasccmentioning

confidence: 99%

Deformation Structure in Highly Irradiated Stainless Steels

Nishioka¹,

Fukuya²,

Fujii³

et al. 2008

J. Nucl. Sci. Technol.

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Surface steps and deformation microstructure in cold-worked SUS316 stainless steels irradiated to 4 and 35 dpa (displacements per atom) were examined after being deformed by uniaxial tensile stress at 320 C at a slow or fast strain rate. Dislocation channeling was the predominant mode of deformation near the surface at the slow strain rate. Twinning was dominant at the fast strain rate whereas twinning and nanotwin formation occurred in the locally stressed area at the slow strain rate. Deformation heterogeneity measured using the spacing of coarse surface steps induced by dislocation channels increased with increasing dose from 4 to 35 dpa. Grain boundary separation occurred when dislocation pileups and high normal stress on the grain boundary plane coexisted, which likely was a precursor of intergranular cracking without any environmental factor.

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“…The materials examined were irradiated thimble tubes made of a cold-worked SUS 316 stainless steel, which were exposed to high neutron flux in fuel assemblies and have been widely used for IASCC studies at high doses. [13][14][15][16][17] Careful sampling enabled us to obtain data in various irradiation conditions due to the gradient of neutron flux and temperature along the height of the core. In this paper, the results of transmission electron microscopy (TEM) and microanalyses together with gas measurement and hardness measurements are described in the dose range of 0.7 to 73 dpa.…”

Section: Introductionmentioning

confidence: 99%

Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation

Fukuya¹,

Fujii²,

Nishioka³

et al. 2006

J. Nucl. Sci. Technol.

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The evolution of microstructures and microchemistry was examined by transmission electron microscopy in coldworked SUS 316 stainless steel components irradiated in a pressurized water reactor to 1-73 dpa at 565-596 K. Homogenous nucleation of dislocation loops, helium bubbles and 0 precipitates was detected. The dislocation loops consisted of a high density of Frank loops and black dots. The black dots are considered to be small Frank loops, some fraction of which could be vacancy-type. The size distribution showed a double peak, which remained unchanged up to 73 dpa, suggesting that the dislocation structure was saturated under a balance of nucleation and disappearance. The helium bubbles were extremely dense and fine, resulting in swelling of less than 0.1%. Such bubble structure was formed under irradiation with a high He/dpa ratio. The 0 precipitation was detected at doses higher than 4 dpa with an increasing density for higher doses. The measured radiation hardening was almost explained by these visible microstructural features. Radiation-induced segregation at grain boundaries was confirmed to continuously develop up to 73 dpa whereas no significant segregation could be detected at Frank loops.

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Stress corrosion cracking on irradiated 316 stainless steel

Cited by 34 publications

References 6 publications

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C

Deformation Structure in Highly Irradiated Stainless Steels

Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation

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Stress corrosion cracking on irradiated 316 stainless steel

Cited by 34 publications

References 6 publications

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300&deg;C

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300&deg;C

Deformation Structure in Highly Irradiated Stainless Steels

Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation

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Product

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Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C

Effects of Implanted Deuterium on <I>In-Situ</I> Irradiation Fatigue Behaviors of Cold-Worked 316 Stainless Steel at 60 and 300°C