Studies of tritiated co-deposited layers in TFTR-Reference-Cited by-同舟云学术

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Studies of tritiated co-deposited layers in TFTR

Published:2001-03 Issue: Volume:290-293 Page:486-490
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Skinner C.H.,Gentile C.A.,Ascione G.,Carpe A.,Causey R.A.,Hayashi T.,Hogan J.,Langish S.,Nishi M.,Shu W.M.,Wampler W.R.,Young K.M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference28 articles.

1. In-vessel tritium retention and removal in ITER

2. Results from deuterium-tritium tokamak confinement experiments

3. Deuterium–tritium plasmas in the Joint European Torus (JET): Behavior and implications

4. Measurements of tritium retention and removal on the Tokamak Fusion Test Reactor

5. Tritium retention and clean-up in JET

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1. Tritium decontamination in vacuum vessel after deuterium plasma experiment due to air exposure;Fusion Engineering and Design;2023-07

2. Radiological source terms estimation for the Divertor Tokamak Test (DTT) facility;Fusion Engineering and Design;2022-07

3. Joint European Torus;Magnetic Fusion Energy;2016

4. The Tokamak Fusion Test Reactor;Magnetic Fusion Energy;2016

5. Resolution of Fission and Fusion Technology Integration Issues: An Upgraded Design Concept for the Subcritical Advanced Burner Reactor;Nuclear Technology;2014-07

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