Effect of Hold Time and Frequency on the Fatigue Crack Growth Rate of Irradiated Cold-Worked Type 316 Stainless Steel

Jitsukawa, Shiro; Umino, Akira; Takahashi, Ichihiko; Iida, Shuji; Adachi, M; Suzuki, Kenichi; Hishinuma, A.

doi:10.1520/stp17932s

Cited by 3 publications

(1 citation statement)

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“…6, the fracture mode of the irradiated specimen fatigue-tested with De t of 0.5% was found to be a channel fracture. Channel fracture [15][16][17] and similar cleavage fracture [18,19] were reported after fatigue tests at De t of about 0.5% in irradiated austenitic stainless steels. In martensitic steels tested by cyclic stress, however, channel fracture has not been reported previously.…”

Section: Discussionmentioning

confidence: 54%

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa

Miwa¹,

Jitsukawa²,

Yonekawa³

2004

Journal of Nuclear Materials

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Section: Discussionmentioning

confidence: 54%

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa

Miwa¹,

Jitsukawa²,

Yonekawa³

2004

Journal of Nuclear Materials

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Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel

Jitsukawa¹,

Hishinuma²,

Suzuki³

1996

Effects of Radiation on Materials: 17th International Symposium

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Fatigue crack growth rates (da/dN)in an irradiated cold worked 316 stainless steel were obtained at temperatures of 298, 573 and 673 K. Specimens were prepared from a duct material, which irradiated at 683 K to 20 displacements per atom in an experimental fast breeder reactor. Fatigue loading caused channel fracture to occur in the irradiated material. This was accompanied by acceleration of da/dN. Both the increment of da/dN and the fraction of channel fracture in fracture surface became larger with stress intensity factor range at temperatures of 573 and 673 K, but they were not at 298 K. Results indicate that irradiation induced channel fracture increased da/dN.

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Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals

Tavassoli

Picker

Wareing

1996

Effects of Radiation on Materials: 17th International Symposium

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Data on the influence of low dose 400–550°C irradiation on the mechanical properties of structural steels (Types 304, 316, 316L, 316H and 316L(N) and associated weld metals) at temperatures from 20°C to 750°C, have been compiled from published literature and the results of British, Dutch, French and German laboratories. Properties evaluated include tensile, impact, creep, fatigue, and creep-fatigue. The preliminary results, which cover the dose range from 0 to 5 displacements per atom (and/or up to 9 appm helium) are presented as comparisons between irradiated and unirradiated control data, covering a range of strength and cyclic properties. The results show that low dose irradiation can have a significant influence on the properties, i.e.:• increases in tensile proof strength,• reductions in tensile ductility,• decreases in impact energy,• reductions in creep-rupture strength and ductility, and • reductions in creep-fatigue endurance. By considering the influence of irradiation temperature and dose level, the results are rationalised in terms of irradiation hardening and grain boundary embrittlement mechanisms.

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Effect of Hold Time and Frequency on the Fatigue Crack Growth Rate of Irradiated Cold-Worked Type 316 Stainless Steel

Cited by 3 publications

References 0 publications

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa

Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel

Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals

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