Overview of the Japanese mock-up tests for ITER high heat flux components-Reference-Cited by-同舟云学术

Overview of the Japanese mock-up tests for ITER high heat flux components

Published:1998-09 Issue: Volume:39-40 Page:219-225
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Akiba M.,Suzuki S.

Publisher

Elsevier BV

Subject

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

Reference6 articles.

1. ITER, ITER EDA Documentation Series, No.7, IAEA, Vienna, 1996.

2. M. Araki, Y. Kude, Y. Sohda, K. Nakamura, K. Sato, S. Suzuki, M. Akiba, Development of 3D-based CFC with high thermal conductivity for fusion application, In: C. Varandas, F. Serra (Eds.), Fusion Technol. 1996, Elsevier Science, (1997) 359–362.

3. K. Sato, K. Nakamura, S. Suzuki, M. Araki, M. Dairaku, K. Yokoyama, M. Akiba, High heat flux test of CVD-tungsten coated Cu heat sink divertor mock-up, Fusion Technol. 30 (1996) 769–773.

4. M. Akiba, S. Suzuki, S. Satoh, K. Nakamura, M. Araki, Y. Ohara, Development of plasma-facing components for fusion experimental reactors at JAERI, In: C. Varandas, F. Serra (Eds.), Fusion Technol. 1996, Elsevier Science, (1997) 307–310.

5. S. Suzuki, M. Araki, K. Sato, K. Nakamura, M. Akiba, High heat flux experiments on a saddle-shaped divertor mock-up, Proc. 16th International Conference on Fusion Energy, 7–11 October 1996, IAEA, Vienna, (1997) 565–570.

Cited by 38 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. Investigation of tungsten/MA956 steel diffusion bonding with an Nb/Ni composite interlayer;International Journal of Modern Physics B;2020-05-10

2. Graphite and Carbon Fiber Composite for Fusion;Comprehensive Nuclear Materials;2020

3. Heat Transfer Performance of a Water Impinging Jet Flow in a Metal Particle Bed;Fusion Science and Technology;2017-09-18

4. Gas-Cooled Divertor Concept with High Thermal Conductivity Porous Media;Fusion Science and Technology;2015-10

5. Preliminary R&D on flat-type W/Cu plasma-facing materials and components for Experimental Advanced Superconducting Tokamak;Physica Scripta;2014-04-01