Fatigue Behavior of Type 316 Stainless Steel Irradiated in a Mixed Spectrum Fission Reactor Forming Helium

Grossbeck, M.L.; Liu, Kenneth C.

doi:10.13182/nt82-a32987

Cited by 52 publications

(3 citation statements)

References 10 publications

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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: 55%

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: 55%

Fatigue properties of F82H irradiated at 523 K to 3.8 dpa

Miwa¹,

Jitsukawa²,

Yonekawa³

2004

Journal of Nuclear Materials

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“…The situation can be quite different in the case of fusion devices where ICFRs and the next generation of tokamaks are expected to employ cyclic operation, [99,100];. and where very high helium production rates are expected in addition to the atomic displacements.…”

Section: Fatiguementioning

confidence: 99%

“…In the first study, 20% cold-worked AISI 316 stainless-steel specimens have been irradiated in a mixed-spectrum reactor (HFIR), creating up to 15 dpa and 900 ppm He. Then, post-irradiation fatigue tests with strain rates of 4 X 10" 3 and 4 X 10~2s~1 were performed in vacuum at the irradiation temperatures of 430 and 550°C, respectively [99,100]. The resulting numbers of cycles to failure are plotted in Fig.…”

Section: Fig41 Fatigue Life Of 20% Cold-worked Aisi316 Stainless Stee...mentioning

confidence: 99%

The influence of helium on the bulk properties of fusion reactor structural materials

Ullmaier¹

1984

Nucl. Fusion

363

115

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Radiation-induced deterioration of fission reactor materials is dominated by displacement damage. In fusion reactors, the influence of (n,a) produced helium upon material deterioration is regarded to be of equal importance because of the high nuclear reaction rate caused by the high-energy fusion neutrons. In this review, the mechanisms and the anticipated rates of helium generation in fusion materials are discussed; helium introduction techniques simulating fusion conditions are reviewed in some detail and the atomistic behaviour of helium in metals as well as the nucleation and growth of helium bubbles are briefly surveyed. These phenomena are the main cause for the influence of helium on macroscopic material properties such as tensile strength, creep and fatigue behaviour and swelling. Typical examples of experimental results of material deterioration and first attempts at their theoretical modelling are given in the main part of the review. It is shown that helium effects can be the determining factor for the lifetime of fusion reactor components, particularly at high temperatures. The review concludes with an outlook on future investigations of helium effects and a call for a systematic approach in the development of helium-resistant alloys.

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