A comparative study of deuterium ingress from solution into Zr, Zircaloy-2 and Zr-2.5wt.% Nb by nuclear reaction analysis at the liquid-solid interface
Author:
Publisher
Elsevier BV
Subject
Instrumentation,Nuclear and High Energy Physics
Reference12 articles.
1. Potential structural material problems in a hydrogen energy system
2. Proc. 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems;Cox,1986
3. Proc. 7th Int. Symp. on Zirconium in the Nuclear Industry;Urbanic,1987
4. The effect of anodic oxidation on near-surface deuterium in Zr-2.5 wt.% Nb
5. In situ NRA studies of hydrogen ingress into Zr-2.5 wt.% Nb at the liquid-solid interface
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1. Effect of elements on hydrogen pickup and corrosion behavior of ZrFeCr alloys in 500°C steam;Nuclear Engineering and Design;2014-07
2. The effect of alloying modifications on hydrogen uptake of zirconium-alloy welding specimens during corrosion tests;Journal of Nuclear Materials;2006-04
3. Impact of intermetallic precipitates on hydrogen distribution in the oxide layers formed on zirconium alloys in a steam atmosphere: a 2D(3He,p)α nuclear analysis study in microbeam mode;Journal of Alloys and Compounds;1998-03
4. CHEMICAL PROPERTIES OF A Nb/Zr INTERFACE STUDIED BY XPS;Surface Review and Letters;1997-02
5. XPS investigations of the reactivities of oxidized interfaces formed by deposition on a gold substrate;Applied Surface Science;1996-12
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