Susceptibility of Sensitized Type 304 Stainless Steel to Intergranular Stress Corrosion Cracking in Simulated Boiling-Water Reactor Environments

Author:

Saito N.,Kikuchi E.,Sakamoto H.,Kuniya J.,Suzuki S.

Publisher

NACE International

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Cited by 6 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Heat treatment effect on sensitization behavior of 304 grade stainless steel;AIP Conference Proceedings;2023

2. The Effect of H2O2on ECP Under a Variety of Flow Rate and Temperature;Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2013-10-04

3. Role of grain boundary nature and residual strain in controlling sensitisation of type 304 stainless steel;Corrosion Science;2013-01

4. Electrochemical behaviour of stainless steel in PWR primary coolant conditions: Effects of radiolysis;Journal of Nuclear Materials;2011-12

5. Radiation Chemistry in Nuclear Engineering;Charged Particle and Photon Interactions with Matter;2010-12-13

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