Distribution and release of tritium in high-temperature gas-cooled reactors as a function of design, operational, and material parameters-Reference-Cited by-同舟云学术

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Distribution and release of tritium in high-temperature gas-cooled reactors as a function of design, operational, and material parameters

Published:1974-06-01 Issue: Volume: Page:
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Author:

Compere E.L.,Freid S.H.,Nestor C.W.

Publisher

Office of Scientific and Technical Information (OSTI)

Cited by 6 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 corrosion effects of neutron activation of 2LiF-BeF2 (FLiBe);Nuclear Materials and Energy;2023-03

2. Tritium Transport and Distribution in a High-Temperature Gas-Cooled Reactor;Fusion Science and Technology;2020-03-25

3. Status and Plan of the System Codes Development for ITER Test Blanket Module and Fusion Breeding Blanket in Korea;Fusion Science and Technology;2013-09

4. Analysis of Tritium Behavior in Very High Temperature Gas-Cooled Reactor Coupled with Thermochemical Iodine-Sulfur Process for Hydrogen Production;Journal of Nuclear Science and Technology;2008-11

5. Occupational Radiation Exposures at a Fusion Power Station;Nuclear Technology - Fusion;1982-10

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