Výsledky vyhledávání - "Roger W. Staehle"

Stress Corrosion Cracking Growth of Alloy 800NG in Pressurized Water Reactor Primary Water

Autor: R. L. Tapping, Takuyo Yamada, Roger W. Staehle, Tomoki Miyamoto, Koji Arioka

Publikováno v: Corrosion. 74:24-36

The primary purpose of this research is to examine the stress corrosion cracking (SCC) resistance of Alloy 800NG in pressurized water reactor (PWR) primary water and pressurized heavy water reactor (PHWR) primary water. Rates of SCC growth of 20% col

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::cf83042da961c8e26eb3c1123a662b84
https://doi.org/10.5006/2572

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Degradation of Alloy 690 After Relatively Short Times

Autor: Roger W. Staehle, Tomoki Miyamoto, Takuyo Yamada, Koji Arioka, T. Terachi

Publikováno v: CORROSION. 72:1252-1268

The purpose of this work is to understand quantitative processes which underlie the initiation of stress corrosion cracking (SCC) of cold-worked, thermally treated Alloy 690 after long-term exposures in high-temperature water. Long-term stress corros

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1a03b3976c34715233d65b007a6b0e1e
https://doi.org/10.5006/2107

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Comparison of Corrosion Resistance of UNS N06690TT and UNS N08800SN in Simulated Primary Water with Various Concentrations of Dissolved Oxygen

Autor: Zhiming Zhang, Jiazhen Wang, Xiaohui Li, Fa Huang, Jianqiu Wang, Roger W. Staehle

Publikováno v: CORROSION. 70:598-614

Corrosion behaviors of UNS N06690TT and N08800SN in simulated pressurized water reactor (PWR) primary water containing three concentrations of dissolved oxygen (DO) was studied by open-circuit potential (OCP), electrochemical impedance spectroscopy (

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5a6f370e3423bc41168cd8ba3ca55787
https://doi.org/10.5006/1167

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Elektronická kniha

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors : The Coriou Effect

Autor: Damien Feron, Roger W Staehle

Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloy

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Historical Experience Providing Bases for Predicting Corrosion and Stress Corrosion in Emerging Supercritical Water Nuclear Technology: Part 3—Review

Autor: Roger W. Staehle, Xiong Ru

Publikováno v: Corrosion. 69:423-447

This review assesses past experiences from superheated fossil plants, supercritical fossil plants, superheated nuclear plants, and light water reactors from the late 1940s until the present. Data from the development and operation of these plants are

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::23c9ebd28332751068b8d3f458c77161
https://doi.org/10.5006/0726.part3

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