Postirradiation Creep of Annealed Type 316 Stainless Steel

Lovell, A.J.

doi:10.13182/nt72-a31198

Nuclear Technology

1972

DOI: 10.13182/nt72-a31198

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Postirradiation Creep of Annealed Type 316 Stainless Steel

A.J. Lovell

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1976

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Cited by 9 publications

(1 citation statement)

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“…FIG.2 7. Creep curves of unirradiated and reactor pre-irradiated AISI 316 stainless-steel specimens tested at 760°C (after Lovell[89];.…”

mentioning

confidence: 99%

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

Ullmaier¹

1984

Nucl. Fusion

371

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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“…FIG.2 7. Creep curves of unirradiated and reactor pre-irradiated AISI 316 stainless-steel specimens tested at 760°C (after Lovell[89];.…”

mentioning

confidence: 99%

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

Ullmaier¹

1984

Nucl. Fusion

371

115

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In-reactor creep rupture of 20% cold-worked AISI 316 stainless steel

Lovell¹,

Chin²,

Gilbert³

1981

J Mater Sci

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The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steels

James¹

1976

Journal of Nuclear Materials

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Postirradiation Creep of Annealed Type 316 Stainless Steel

Cited by 9 publications

References 6 publications

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

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

In-reactor creep rupture of 20% cold-worked AISI 316 stainless steel

The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steels

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