Evaluation of self-welding susceptibility of an austenitic stainless steel (alloy D9) in sodium-Reference-Cited by-同舟云学术

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Evaluation of self-welding susceptibility of an austenitic stainless steel (alloy D9) in sodium

Published:2008-02 Issue:1-2 Volume:374 Page:1-8
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kumar Hemant,Albert S.K.,Ramakrishnan V.,Meikandamurthy C.,Amarendra G.,Bhaduri A.K.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference4 articles.

1. Experimental study of self-welding of materials in high temperature liquid sodium

2. Investigation of Self-Welding Rate of Structural Materials in Liquid Sodium

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1. Performance evaluation and qualification of hard coatings used in absorber rod drive mechanism of Indian fast breeder reactor;Nuclear Engineering and Design;2024-02

2. Self-welding of Inconel 617 under high-pressure-high-temperature conditions for nuclear reactors;Nuclear Engineering and Design;2021-01

3. Friction and Wear Behavior of CrN Coating on 316L Stainless Steel in Liquid Sodium at Elevated Temperature;Tribology International;2020-03

4. Friction and wear behaviour of Ni-Cr-B hardface coating on 316LN stainless steel in liquid sodium at elevated temperature;Journal of Nuclear Materials;2017-11

5. Short Communication on “Self-welding susceptibility of NiCr-B hardfaced coating with and without NiCr-B coating on 316LN stainless steel in flowing sodium at elevated temperature”;Journal of Nuclear Materials;2017-02

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