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Samson Hettiarachchi

Researcher at General Electric

Publications -  34
Citations -  382

Samson Hettiarachchi is an academic researcher from General Electric. The author has contributed to research in topics: Noble metal & Corrosion. The author has an hindex of 12, co-authored 34 publications receiving 382 citations. Previous affiliations of Samson Hettiarachchi include Wilmington University.

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Patent

In-situ palladium doping or coating of stainless steel surfaces

TL;DR: In this article, a method for reducing corrosion of metal components in a water-cooled nuclear reactor is presented. But the method is limited to the case of a single platinum group metal, e.g. palladium.
Patent

Application of catalytic nanoparticles to high temperature water systems to reduce stress corrosion cracking

TL;DR: In this paper, a method and system for reducing stress corrosion cracking in a hot water system, such as a nuclear reactor, by reducing the electrochemical corrosion potential of components exposed to high temperature water within the structure is presented.
Patent

Co-deposition of palladium during oxide film growth in high-temperature water to mitigate stress corrosion cracking

TL;DR: In this paper, a method for improving the performance and longevity of coatings of metal deposited from aqueous solutions of inorganic, organic or oraganometallic metal compounds was proposed.
Patent

Method for monitoring noble metal distribution in reactor circuit during plant application

TL;DR: In this paper, a method for ensuring the distribution of noble metal in the reactor circuit during plant application without measuring the reactor water for noble metal content by chemical analysis is proposed, which involves the measurement of electrochemical corrosion potential in an autoclave or a high-flow test section.
Patent

Modification of oxide film electrical conductivity to maintain low corrosion potential in high-temperature water

TL;DR: In this article, a method for mitigating general corrosion and crack initiation and growth on the surface of a metal component in a water-cooled nuclear reactor is presented, where a compound containing a non-noble metal such as zirconium or titanium is injected into the water of the reactor in the form of a solution or suspension.