Affiliation:
1. Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610041, China.
Abstract
Forged Type 316NG austenitic stainless steel is commonly used to fabricate primary coolant pipe in advanced pressurized water reactor systems, but it is subject to corrosion fatigue cracking in primary coolant environments. In this study, the fatigue crack growth of Type 316NG austenitic stainless steel in 325°C water was investigated. The corrosion fatigue effect in 325°C water was mainly correlated to the crack growth rate and load frequency. A maximum Fen (environment corrected factor) value up to 100 was observed at f = 0.005 Hz, ΔK = 13 MPa√m. The dissolved oxygen tended to have little influence on the fatigue crack growth. The crack path was deflected and branched. Most secondary cracks tended to be initiated from grain boundaries.
Subject
General Materials Science,General Chemical Engineering,General Chemistry
Cited by
6 articles.
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