Fatigue Behavior of Type 316 Stainless Steel Irradiated in a Mixed Spectrum Fission Reactor Forming Helium-Reference-Cited by-同舟云学术

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

Published:1982-09 Issue:3 Volume:58 Page:538-547
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Grossbeck Martin L.¹,Liu Kenneth C.¹

Affiliation:

1. Oak Ridge National Laboratory, Metals and Ceramics Division Oak Ridge, Tennessee 37830

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT82-A32987

Reference22 articles.

1. Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures

2. Low cycle fatigue and hold time comparisons of irradiated and unirradiated type 316 stainless steel

3. C. E. De Bogdan, “Tensile and Fatigue Data for Irradiated and Unirradiated AISI 319 Stainless Steel and Titanium-5 percent Aluminum-2.5 percent Tin: Application of the Method of Universal Slopes,” NASA TMX-2883, National Aeronautics and Space Administration (1973).

4. Fatigue Behavior of Irradiated Thin-Section Type 348 Stainless Steel at 550 F (288 C)

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