Postirradiation Mechanical Properties of Types 304 and 304 +0.15% Titanium Stainless Steel-Reference-Cited by-同舟云学术

Postirradiation Mechanical Properties of Types 304 and 304 +0.15% Titanium Stainless Steel

Published:1973-01 Issue:1 Volume:17 Page:24-37
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bloom E. E.¹,Stiegler J. O.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/NT73-A31251

Reference25 articles.

1. E. E. BLOOM, “An Investigation of Fast Neutron Radiation Damage in an Austenitic Stainless Steel,” ORNL-4580, Oak Ridge National Laboratory (1970).

2. Radiation damage in annealed type 304 stainless steel

3. R. BULLOUGH and R. C. PERRIN, in Irradiation Effects on Structural Alloys for Nuclear Reactor Applications, Spec. Tech. Publ. 484, p. 317, American Society for Testing and Materials (1971).

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