New Cast High-Strength Alloy Grades by Structure Control

Beck, F. H.; Schoefer, E. A.; Flowers, J.; Fontana, Mars G.

doi:10.1520/stp43742s

Cited by 8 publications

(3 citation statements)

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“…Recourse to the composition ranges for these casting grades, coupled with use of the Schoefer Diagram [77][78] (Fig. 16), which is the casting-industry analog of the weldors' DeLong diagram for representation of regions of phase stability, indicates that both of these alloys can be manufactured with up to 30$ ferrite.…”

Section: Austenitic Stainless Steelsmentioning

confidence: 99%

Austenitic stainless steels for cryogenic service

Dalder¹,

Juhas²

1985

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Section: Austenitic Stainless Steelsmentioning

confidence: 99%

Austenitic stainless steels for cryogenic service

Dalder¹,

Juhas²

1985

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“…Beck et al [6] showed that the tensile and yield strengths of CASS materials increase with ferrite content at both room and elevated temperatures. In addition, ferrite phase can also improve the resistance to sensitization, and therefore reduce the susceptibility to stress corrosion cracking (SCC) [7] [8].…”

Section: Introductionmentioning

confidence: 99%

Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel

Chen

Alexandreanu

Chen

et al. 2015

Journal of Nuclear Materials

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“…Since hardening mechanisms by thermal-mechanical treatments cannot be easily implemented in castings, the strength of CASS mainly relies on the ferrite-austenite duplex microstructure. Beck et al 13 showed that the tensile and yield strengths of CASS increase with ferrite content up to 40% at both room and elevated temperatures. The strengthening effect of ferrite phase is attributed to ferrite-austenite boundaries and can be explained with the Hall-Petch model.…”

Section: Introductionmentioning

confidence: 99%

Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels

Chen¹,

Alexandreanu²,

Natesan³

2013

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Cast austenitic stainless steels are used in the cooling system of light water reactors for components with complex shapes, such as pump casings, valve bodies, and coolant piping. In the present study, crack growth rate and fracture toughness JR curve tests were performed on irradiated cast stainless steels in low-corrosion-potential environments (low-dissolved-oxygen high-purity water or simulated pressurized water reactor environment) at 320°C. Both asreceived and thermally aged materials were included to investigate the combined effect of thermal aging and irradiation embrittlement on the fracture behavior of cast stainless steels. The samples were irradiated to approximately 0.08 dpa at the Halden reactor. Good resistance to corrosion fatigue and stress corrosion cracking was observed for all samples. Thermal aging had little effect on the crack growth behavior at this dose level. Cleavage-like fracture was the dominant cracking morphology during the crack growth rate tests, and the ferrite phase was deformed to a lesser extent compared with the surrounding austenite phase. The fracture toughness results showed a dominant effect of neutron irradiation, and the fracture resistances were decreased considerably for all cast specimens regardless of their thermal aging conditions. The reduction in fracture toughness was more significant in the unaged than thermally aged materials. Nonetheless, the fracture toughness values of thermally aged specimens were about 30% lower than their unaged counterparts, suggesting a combined effect of thermal aging and neutron irradiation in cast stainless steel. Executive SummaryCast austenitic stainless steel (CASS) is used in the cooling system of light water reactors for components with complex shapes, such as pump casings, valve bodies, coolant piping, control rod guide tube spacers, etc. In contrast to a fully austenitic microstructure of wrought stainless steel (SS), CASS consists of a ferrite-austenite duplex microstructure. A certain amount of delta ferrite phase is intentionally designed into CASS and SS weld metals to engineer against hot cracking. However, the ferrite phase is vulnerable to thermal aging embrittlement after longterm exposure to reactor coolant. In addition, neutron irradiation can decrease the fracture resistance of CASS significantly. It is suspected that a combined effect of thermal aging and irradiation embrittlement could reduce the fracture resistance even further to a level neither of these degradation mechanisms can impart alone. While the thermal aging embrittlement of CASS has been studied extensively, there are no data available at present with regard to the combined effect of thermal aging and irradiation embrittlement. A test program has been initiated to investigate the joint effect of thermal aging and irradiation damage on the cracking susceptibility and fracture resistance of CASS.Crack growth rate (CGR) and fracture toughness JR curve tests were conducted on three grades of CASS (CF-3, CF-8 and CF-8M) containing high levels...

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New Cast High-Strength Alloy Grades by Structure Control

Cited by 8 publications

References 0 publications

Austenitic stainless steels for cryogenic service

Austenitic stainless steels for cryogenic service

Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel

Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels

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