The effects of irradiation and testing temperature on tensile behaviour of stainless steels

Bailat, Claude; Almazouzi, A.; Baluc, N.; Schäublin, R.; Gröschel, F.; Victoria, M.

doi:10.1016/s0022-3115(00)00083-0

Cited by 47 publications

(31 citation statements)

References 9 publications

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“…[61] The rapid removal of a dense population of small obstacles impeding dislocation motion could result in a change in deformation mode and, hence, cracking behavior during annealing. This is consistent with the work of Bailat et al, [62] who reported a possible correlation between deformation mode and IASCC in neutron-irradiated stainless steels. Bailat et al found localized deformation (channeling and microtwinning) in a susceptible 304 SS alloy using TEM analysis.…”

Section: Implications For Iasccsupporting

confidence: 93%

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors

Was¹,

Atzmon²

2003

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Executive SummaryThe overall goal of the project is to determine the mechanism of irradiation assisted stress corrosion cracking (IASCC). IASCC has been linked to hardening, microstructural and microchemical changes during irradiation. Unfortunately, all of these changes occur simultaneously and at similar rates during irradiation, making attribution of IASCC to any one of these features nearly impossible to determine. The strategy set forth in this project is to develop means to separate microstructural from microchemical changes to evaluate each separately for their effect on IASCC. In the first part, post irradiation annealing (PIA) treatments are used to anneal the irradiated microstructure, leaving only radiation induced segregation (RIS) for evaluation for its contribution to IASCC. The second part of the strategy is to use low temperature irradiation to produce a radiation damage dislocation loop microstructure without radiation induced segregation in order to evaluate the effect of the dislocation microstructure alone.A radiation annealing model was developed based on the elimination of dislocation loops by vacancy absorption. Results showed that there were indeed, time-temperature annealing combinations that leave the radiation induced segregation profile largely unaltered while the dislocation microstructure is significantly reduced. Proton irradiation of 304 stainless steel irradiated with 3.2 MeV protons to 1.0 or 2.5 dpa resulted in grain boundary depletion of chromium and enrichment of nickel and a radiation damaged microstructure. Post irradiation annealing at temperatures of 500 -600°C for times of up to 45 min. removed the dislocation microstructure to a greater degree with increasing temperatures, or times at temperature, while leaving the radiation induced segregation profile relatively unaltered. Constant extension rate tensile (CERT) experiments in 288°C water containing 2 ppm O 2 and with a conductivity of 0.2 mS/cm and at a strain rate of 3 x 10 -7 s -1 showed that the IASCC susceptibility, as measured by the crack length per unit strain, decreased with very short anneals and was almost completely removed by an anneal at 500°C for 45 min. This annealing treatment removed about 15% of the dislocation microstructure and the irradiation hardening, but did not affect the grain boundary chromium depletion or nickel segregation, nor did it affect the grain boundary content of other minor impurities. These results indicate that RIS is not the sole controlling feature of IASCC in irradiated stainless steels in normal water chemistry. DE-FG07-99ID13768Final Report 3The isolation of the irradiated microstructure was approached using low temperature irradiation or combinations of low and high temperature irradiations to achieve a stable, irradiated microstructure without RIS. Experiments were successful in achieving a high degree of irradiation hardening without any evidence of RIS of either major or minor elements. The low temperature irradiations to doses up to 0.3 dpa at T<75°C were also very succ...

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Section: Implications For Iasccsupporting

confidence: 93%

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors

Was¹,

Atzmon²

2003

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“…These coefficients have the advantage of accounting for the fact that the elastic shear modulus of the present Cu potentials is about half that of SS. As a result, critical unpinning stresses in SS are expected to be higher than those reported here: the use of the present interaction coefficients for SS gives a maximum resistance as high as 1.59 × 75 GPa×0.26 nm/50 nm ∼ 600 MPa, of the order of the critical twinning RSS at 600K (= 2 × 35 mJ.m −2 /1.45Å ∼ 500 MPa), which could explain why twinning is locally observed, even at 600 K [27,28]. Note that the critical twinning stress does not depend on the shear modulus.…”

Section: Critical Unpinning Stressesmentioning

confidence: 56%

“…[24,25], twin nucleation is favored by the presence of Frank loops. The second mode of deformation, observed at temperatures higher than 600 K and low strain rates, is dislocation channeling [26][27][28]. The change in deformation mode comes from two effects.…”

mentioning

confidence: 99%

Atomic-scale plasticity in the presence of Frank loops

Nogaret

Robertson

Rodney

2007

Philosophical Magazine

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“…In austenitic stainless steels there is a region of high radiation hardening and low ductility for irradiations and tests conducted at around 300 o C [51][52][53][54][55][56][57][58]. Most of such irradiations have been made to doses >>1 dpa, and DCD has been observed in the low ductility specimens [54,[58][59][60]. DCD also occurs in specimens of stainless steel strained after high dose rate ion bombardments at irradiation temperature up to 500 o C and doses of 1-10 dpa where the radiation damage microstructures are similar to those for neutron irradiations at temperatures around 300 o C [61][62][63][64].…”

Section: Phasementioning

confidence: 99%

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

Farrell¹

2003

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The effects of irradiation and testing temperature on tensile behaviour of stainless steels

Cited by 47 publications

References 9 publications

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors

Atomic-scale plasticity in the presence of Frank loops

MAPPING FLOW LOCALIZATION PROCESSES IN DEFORMATION OF IRRADIATED REACTOR STRUCTURAL ALLOYS - FINAL REPORT. Nuclear Energy Research Initiative Program No. MSF99-0072. Period: August 1999 through September 2002. (ORNL/TM-2003/63)

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