The occurrence of an ordered FCC phase in neutron irradiated M316 stainless steel

Cawthorne, C.; Brown, C. M.

doi:10.1016/0022-3115(77)90149-0

Cited by 43 publications

(11 citation statements)

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“…In addition, the fraction of G phase significantly increases next to that of γ'. The prediction that γ' appears as a dominant RIP over G phase in irradiated 316 ASS is consistent with experimental observations [10][11][12][13][14][15][16][17]. Fig.…”

Section: Resultssupporting

confidence: 89%

“…Radiation-induced phases (RIPs) are precipitates that appear only under irradiation but not for corresponding thermal conditions [3]. γ' and G phases are the typical RIPs observed in ASSs [10][11][12][13][14][15][16][17][18][19][20]. Of the various grades of ASSs, 316 may be the most susceptible to the formation of γ' and G phases due to the higher Ni content.…”

Section: Introductionmentioning

confidence: 99%

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Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation

Shim

Povoden-Karadeniz

Kozeschnik

et al. 2015

Journal of Nuclear Materials

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The long-term evolution of precipitates in type 316 austenitic stainless steels at 400 o C has been simulated using a numerical model based on classical nucleation theory and the thermodynamic extremum principle. Particular attention has been paid to the precipitation of radiation-induced phases such as γ' and G phases. In addition to the original compositions, the compositions for radiation-induced segregation at a dose level of 5, 10 or 20 dpa have been used in the simulation. In a 316 austenitic stainless steel, γ' appears as the main precipitate with a small amount of G phase forming at 10 and 20 dpa. On the other hand, G phase becomes relatively dominant over γ' at the same dose levels in a Ti-stabilized 316 austenitic stainless steel, which tends to suppress the formation of γ'. Among the segregated alloying elements, the concentration of Si seems to be the most critical for the formation of radiationinduced phases. An increase in dislocation density as well as increased diffusivity of Mn and Si significantly enhances the precipitation kinetics of the radiation-induced phases within this model.

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Section: Resultssupporting

confidence: 89%

Section: Introductionmentioning

confidence: 99%

Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation

Shim

Povoden-Karadeniz

Kozeschnik

et al. 2015

Journal of Nuclear Materials

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“…Frequently, c 0 precipitates are observed in superalloys such as Inconel alloys, with compositions of (Ni, Co, Fe, Cr) 3 (Al, Ti) [12,48]. In Type 316 steels, it has been observed following irradiation and thermal ageing in the temperature range 270-540°C with a composition of Ni 3 (Si, Al, Ti, Nb), and a high solubility of the elements Fe, Cr and Mo [48][49][50]. It has been proposed that neutron irradiation has a critical role in c 0 formation, or at least rapidly enhanced the formation kinetics [48].…”

Section: Discussionmentioning

confidence: 99%

Precipitation within localised chromium-enriched regions in a Type 316H austenitic stainless steel

2018

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A Type 316H austenitic stainless steel component containing Cr and impurity element-rich localised regions arising from component fabrication was aged for a prolonged period during service at a temperature of approximately 550°C. These regions make up approximately 5% of the total volume of the microstructure. Previous work has shown that these regions contain ferrite and carbide precipitates and a finer austenite grain size than the adjacent matrix. The present study has used high-resolution transmission electron microscopy combined with compositional microanalysis to show that these regions have a highly complex microstructure containing G phase, chi phase and intragranular c 0 precipitates within the austenite grains. There is phosphorus migration to the chi austenite phase boundary, and the basis for this equilibrium impurity segregation is discussed. A Cr-depleted region was observed surrounding the chi phase precipitates, and the impact of this on the other precipitates is considered. The diversity of precipitates in these Cr-rich regions means that they behave significantly differently to the bulk material under long-term creep conditions leading to preferred nucleation and growth of creep cavities and the formation of localised creep cracks during service.

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“…However, additional information on the low temperature cutoff for several radiation-induced phases was presented in a subsequent paper [74]. Formation of g 0 phase has been reported for fast reactor irradiated M316 stainless steel as low as 270 8C [76]. Unfortunately information on the precipitate size and number density was not provided as a function of temperature and dose.…”

Section: Precipitation During Irradiationmentioning

confidence: 94%

“…Low temperature data (in red) added from Refs. [43,44,[74][75][76]78]. Partially shaded data points are for g 0 phase and solid data points are for either G and related phases or an unidentified phase.…”

mentioning

confidence: 99%

Radiation-induced degradation of stainless steel light water reactor internals

Kenik¹,

Busby²

2012

Materials Science and Engineering: R: Reports

102

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The occurrence of an ordered FCC phase in neutron irradiated M316 stainless steel

Cited by 43 publications

References 0 publications

Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation

Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation

Precipitation within localised chromium-enriched regions in a Type 316H austenitic stainless steel

Radiation-induced degradation of stainless steel light water reactor internals

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