A review of the US joining technologies for plasma facing components in the ITER fusion reactor-Reference-Cited by-同舟云学术

A review of the US joining technologies for plasma facing components in the ITER fusion reactor

Published:1998-10 Issue: Volume:258-263 Page:329-334
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Odegard Jr B.C,Cadden C.H,Watson R.D,Slattery K.T

Publisher

Elsevier BV

Subject

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

Reference19 articles.

1. Fatigue assessment of the conductor jacket for the Next European Torus toroidal field and poloidal field coils

2. D.E. Dombrowski, D. Hashiguchi, JET Final Report, JDO/14691, 1990

3. D. Hashiguchi, JET Final Report, JD9/13197, 1990

4. H. Altmann, E.B. Deksnis, C. Ibbott, C. Sborchia, R. Tivey, R. Viola, Proceedings 15th IEEE Symposium on Fusion Engineering, 11–15 October 1993, Hyanis, MA, USA

5. E. Franconi, G.C. Ceccotti, L. Magnoli, Proceedings Fifth International Conference on Fusion Reactor Materials, 17–21 November 1991, Clearwater, FL, USA

Cited by 28 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. Enhancing the high-temperature thermal evacuation of Cf/C-Mo30Cu joint via grooving 3D heat transfer interface;Applied Thermal Engineering;2024-03

2. Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers;Metals;2023-08-10

3. Tungsten as a Plasma-Facing Material;Comprehensive Nuclear Materials;2020

4. W–steel and W–WC–steel composites and FGMs produced by hot pressing;Fusion Engineering and Design;2015-11

5. Mechanical characterization and modeling of brazed tungsten and Cu–Cr–Zr alloy using stress relief interlayers;Journal of Nuclear Materials;2014-12