Concepedia

SCC growth behaviors of austenitic stainless steels in simulated PWR primary water

Takumi Terachi, Takuyo Yamada, T. Miyamoto, Koji Arioka

Journal of Nuclear Materials · 2012 · 118 citations · 21 references

DOI

Concepts

References

21

Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320°C

Takumi Terachi, Katsuhiko Fujii, Koji Arioka · Journal of Nuclear Science and Technology · 2005 · 181 citations

, , +17

Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content

Sergio Lozano‐Perez, Takuyo Yamada, Takumi Terachi et al. · Acta Materialia · 2009 · 175 citations

, , +17

IGSCC of non-sensitized stainless steels in high temperature water

Peter L. Andresen, Martin M. Morra · Journal of Nuclear Materials · 2008 · 161 citations

, , +9

Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

Gary S. Was, Peter L. Andresen · CORROSION · 2007 · 128 citations

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Cold Work and Temperature Dependence of Stress Corrosion Crack Growth of Austenitic Stainless Steels in Hydrogenated and Oxygenated High-Temperature Water

Takuyo Yamada, Takumi Terachi, Goro Chiba · CORROSION · 2007 · 122 citations

, , +17