The Blanket Interface to TSTA: Requirements for Liquid Lithium Blanket Processing Systems-Reference-Cited by-同舟云学术

The Blanket Interface to TSTA: Requirements for Liquid Lithium Blanket Processing Systems

Published:1988-09 Issue:2P2A Volume:14 Page:657-662
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Clemmer R. G.¹,Finn P. A.¹,Grimm T. L.¹,Sze D. K.¹,Anderson J. L.²,Bartlit J. R.²,Naruse Y.³,Yoshida H.³

Affiliation:

1. Argonne National Laboratory Chemical Technology Division 9700 S. Cass Ave., Argonne, IL 60439

2. Los Alamos National Laboratory Los Alamos, NM 87545

3. Japan Atomic Energy Research Institue Tokai Research Establishment Tokai-mura, Naka-gun, Ibaraki-ken, Japan

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST88-A25209

Reference10 articles.

1. J. L. ANDERSON and R. H. SHERMAN, “Tritium Systems Test Assembly - Design for Major Device Fabrication Review,” Los Alamos National Laboratory, LA-6855-P, June 1977.

2. Experiments on a Ceramic Electrolysis Cell and a Palladium Diffuser at the Tritium Systems Test Assembly

3. see also J. L. Anderson et al. “Development of Tritium Technology for the United States Magnetic Fusion Energy Program,” Los Alamos National Laboratory, LA-UR-80-175 (1980).

4. The Use of Yttrium for the Recovery of Tritium from Lithium at Low Concentrations

5. B. BADGER et al., UWMAK-I, Univ. Wise., UWFDM-68, March 1974.

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Gas analysis in electrochemical extraction of hydrogen from liquid lithium;Fusion Engineering and Design;2024-03

2. Developments of Tritium Technology for Next-Step Fusion Devices under JAERI-DOE (LANL) Collaboration;Journal of Nuclear Science and Technology;1990-12

3. The tritium systems test assembly at Los Alamos National Laboratory;Fusion Engineering and Design;1990-06