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RESEARCH PAPERS

Service Properties of Reactor Structural Steels and Prediction of NPP Equipment Life With PWR-Type Reactors

[+] Author and Article Information
Yu. I. Zvezdin

Central Research Institute for Machine Building Technology, Moscow USSR

D. M. Shur

Brittle Strength Laboratory, Central Research Institute for Machine Building Technology, Moscow USSR

A. A. Popov

Department of Strength Materials and Constructions, Central Research Institute for Machine Building Technology, Moscow USSR

J. Pressure Vessel Technol 113(2), 159-162 (May 01, 1991) (4 pages) doi:10.1115/1.2928741 History: Received April 16, 1991; Online June 17, 2008

Abstract

The results obtained from the experimental investigation of Cr-Ni-Mo-V and Mn-Ni-Mo-V steel service properties used in the USSR reactor building, as well as the static crack resistance KIC versus reference temperature dependence and Paris kinetic diagrams of fatigue crack growth rate in air and water of high parameters, are given.

Copyright © 1991 by The American Society of Mechanical Engineers
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