Degradation modes of austenitic and ferritic–martensitic stainless steels in He–CO–CO2 and liquid sodium environments of equivalent oxygen and carbon chemical potentials-Reference-Cited by-同舟云学术

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Degradation modes of austenitic and ferritic–martensitic stainless steels in He–CO–CO2 and liquid sodium environments of equivalent oxygen and carbon chemical potentials

Published:2013-10 Issue:1-3 Volume:441 Page:633-643
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Gulsoy G.,Was G.S.,Pawel S.J.,Busby J.T.

Funder

the Department of Energy, Office of Nuclear Energy

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. Corrosion of Materials by Liquid NaK Coolant in a Nuclear Power System

2. Fundamental Aspects of Nuclear Reactor Fuel Elements;Olander,1976

3. J.R. Weeks, H.S. Isaacs, Corrosion and deposition of steels and nickel-based alloys in liquid sodium, in: Advances in Corrosion Science and Technology, Springer, Berlin, 1973, 1–66.

4. Enthalpy of formation of disodium acetylide and of monosodium acetylide at 298.15 K, heat capacity of disodium acetylide from 5 to 350 K, and some derived thermodynamic properties

5. The solubility of carbon in sodium

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1. Varied enhancements in mechanical properties and sodium compatibility of Grade 92 by thermomechanical treatments;Materials Science and Engineering: A;2022-01

2. Investigation of flowing liquid zinc erosion and corrosion properties of the Fe–B alloy at various times;Journal of Materials Research;2015-02-13

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