Preliminary Design of a Fusion Reactor Fuel Cleanup System By The Palladium-Alloy Membrane Method
Author:
Affiliation:
1. Tritium Engineering Laboratory, Japan Atomic Energy Research Institute, Division of Thermonuclear Fusion Research, Tokai-mura, Ibaraki-ken, Japan
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST83-A20869
Reference16 articles.
1. J. L. ANDERSON et al. “Tritium Systems Test Assembly, Design for Major Device Fabrication Review,” LA-6855-P, Los Alamos National Laboratory (1977).
2. TSTA Design Team, “Preliminary Safety Analysis Report for the Tritium Systems Test Assembly,” Los Alamos National Laboratory (1979).
3. H. YOSHIDA et al. “Permeabilities of Hydrogen Isotopes Through Pd—25 wt% Ag Alloy Membrane at Comparatively High Pressure and Temperature,” JAERI-M 9677, Japan Atomic Energy Research Institute (1981).
4. Diffusion and permeation of deuterium in palladium-silver at high temperature and pressure
5. Diffusion and solubility of hydrogen in palladium and palladium--silver alloys
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