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Soviet Atomic Energy

, Volume 66, Issue 3, pp 214–217 | Cite as

Effect of simulated nuclear coolant environment on the resistance of the materials of the thin-walled elements and assemblies to fatigue crack growth

  • L. A. Vainer
Articles
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Keywords

Fatigue Fatigue Crack Fatigue Crack Growth Coolant Environment Nuclear Coolant 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Literature Cited

  1. 1.
    The State Committee of the USSR on Standards. Specifications. Calculations and Tests for Evaluating Strength Characteristics in Machine Building. Mechanical Testing Methods for Metals. Determination of the Characteristics of Crack Resistance (Fracture Toughness) during Cyclic Loading. RD 50-345-82 [in Russian], Standartov, Moscow (1983).Google Scholar
  2. 2.
    W. Cullen, H. Watson, R. Taylor, and F. Loss, “Fatigue crack growth rates of irradiated pressure vessel steels in simulated nuclear coolant environment,” J. Nucl. Mater.,96, 261–268 (1981).Google Scholar

Copyright information

© Plenum Publishing Corporation 1989

Authors and Affiliations

  • L. A. Vainer

There are no affiliations available

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