Separation Characteristics of Cryogenic Distillation Column with a Feedback Stream for Separation of Protium Tritium Systems and Tritium-Reference-Cited by-同舟云学术

Separation Characteristics of Cryogenic Distillation Column with a Feedback Stream for Separation of Protium Tritium Systems and Tritium

Published:1982-07 Issue:3 Volume:2 Page:410-425
ISSN:0272-3921
Container-title:Nuclear Technology - Fusion
language:en
Short-container-title:Nuclear Technology - Fusion

Author:

Kinoshita Masahiro¹,Naruse Yuji¹

Affiliation:

1. Japan Atomic Energy Research Institute Division of Thermonuclear Fusion Research Tritium Engineering Laboratory, Tokai-mura, Ibaraki-ken 319-11, Japan

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST82-A20773

Reference17 articles.

1. Hydrogen isotope distillation for fusion power reactors

3. W. R. WILKES, “Tritium Waste Control: October-December 1977,” MLM-2502, p. 10, Mound Laboratories, Miamisburg, Ohio (1978).

4. Isotopic Enrichment of Plasma Exhausts from Controlled Thermonuclear Reactors by Cryogenic Distillation

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