Release Characteristics of Tritium from High-Purity Lithium Oxide-Reference-Cited by-同舟云学术

Release Characteristics of Tritium from High-Purity Lithium Oxide

Published:1985-09 Issue:2P2 Volume:8 Page:2054-2060
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

O’Kula K. R.¹,Vogelsang W. F.²

Affiliation:

1. E. I. du Pont de Nemours & Company Nuclear Engineering Division Building 773-41A Savannah River Laboratory Aiken, South Carolina 29808 (803) 725-5297

2. Fusion Engineering Program Department of Nuclear Engineering University of Wisconsin 1500 Johnson Drive Madison, WI 53706 (608) 262-3374

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST85-A24587

Reference18 articles.

1. R. H. WISWALL and E. WIRSING, “The Removal of Tritium from Fusion Reactor Blankets,” BNL-50748, Brookhaven National Laboratory (1977).

2. Kinetic studies of the trttium release process in neutron-irradiated Li2O and LiOH

3. Thermal release of tritium produced in sintered Li2O pellets

4. Diffusion of tritium in single crystal Li2O

Cited by 4 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. The influence of surface phenomena on in-situ tritium release from lithium oxide;Journal of Nuclear Materials;1991-03

2. In-situ tritium release experiments from solid breeding materials (TTTEx) — Released chemical form of tritium and its diffusivitees in Li2O;Fusion Engineering and Design;1988-01

3. In and out-of-pile tritium extraction from samples of lithium aluminates;Journal of Nuclear Materials;1986-11

4. Post-irradiation tritium recovery from lithium ceramic breeder materials;Journal of Nuclear Materials;1986-11