Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water
Author:
Affiliation:
1. VTT Technical Research Centre of Finland, Kivimiehentie 3, Espoo 02044 VTT, Finland e-mail:
2. VTT Technical Research Centre of Finland, Kemistintie 3, Espoo 02044 VTT, Finland e-mail:
Abstract
Publisher
ASME International
Subject
Nuclear Energy and Engineering,Radiation
Link
http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4037897/6069140/ners_004_01_011016.pdf
Reference14 articles.
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2. Corrosion of Nickel-Base Alloys in Primary Medium of Pressurized Water Reactors: New Insights on the Oxide Growth Mechanisms and Kinetic Modelling;Corros. Sci.,2016
3. The Reproducibility of Corrosion Testing in Supercritical Water—Results of an International Interlaboratory Comparison Exercise;Corros. Sci.,2016
4. Oxidation Parameters of Oxide Dispersion-Strengthened Steels in Supercritical Water;ASME J. Nucl. Eng. Radiat. Sci.,2016
5. Oxidation Model for Construction Materials in Supercritical Water-Estimation of Kinetic and Transport Parameters;Corros. Sci.,2015
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3. Experimental methodologies;Materials and Water Chemistry for Supercritical Water-cooled Reactors;2018
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