Tritium retention in plasma facing components for NET/ITER fusion devices-Reference-Cited by-同舟云学术

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Tritium retention in plasma facing components for NET/ITER fusion devices

Published:1991-12 Issue: Volume:16 Page:393-405
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Federici G.,Wu C.H.,Esser B.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference30 articles.

1. Plasma-material interaction in TFTR;Dilla;J. Nucl. Mater.,1987

2. Wall concepts and density control for JET;Sonnenberg,1986

3. A review of carbon blooms on JET and TFTR;Ulrickson,1990

4. Experience with wall materials in JET and implications for a future ignited tokamak;Rebut,1988

Cited by 7 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. Morphology change and release of tin and lead micro-particles from substrates in hydrogen plasma;Extreme Ultraviolet (EUV) Lithography XII;2021-02-22

2. Atomistic simulations of helium, hydrogen, and self-interstitial diffusion inside dislocation cores in tungsten;Nuclear Fusion;2020-01-10

3. Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation;Journal of Nuclear Materials;2000-06

4. Radioactive Waste from Nuclear Fusion: Decommissioning Wastes from ITER in Four Potential Host Nations;Fusion Technology;1998-08

5. IN-VESSEL TRITIUM INVENTORY AND PERMEATION ASSESSMENTS FOR THE NET DEVICE;Fusion Technology 1992;1993

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