Irradiation tests of radiation hard materials for ITER blanket remote handling system-Reference-Cited by-同舟云学术

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Irradiation tests of radiation hard materials for ITER blanket remote handling system

Published:2017-11 Issue: Volume:124 Page:542-547
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Saito Makiko,Kozaka Hiroshi,Maruyama Takahito,Noguchi Yuto,Nakata Kentaro,Takeda Nobukazu,Kakudate Satoshi

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. Radiation and safety aspects of removal of activated components from the ITER vacuum vessel

2. The ITER remote maintenance system

3. Radiation tolerance qualification for maintenance tasks in the future fusion reactors: from fibre-optic components to robust data links

4. Qualification method for a 1 MGy-tolerant front-end chip designed in 65 nm CMOS for the read-out of remotely operated sensors and actuators during maintenance in ITER

Cited by 4 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 electro-hydraulic mix-drive cantilever arm platform (EMCAP) for general technology research in remote handling for Tokamak;Fusion Engineering and Design;2024-07

2. Irradiation Tests of the Sleeve for the Telescopic Arm of the ITER Blanket Remote Handling System;Plasma and Fusion Research;2024-05-14

3. Mechanical Properties, Radiation Resistance Performances, and Mechanism Insights of Nitrile Butadiene Rubber Irradiated with High-Dose Gamma Rays;Polymers;2023-09-11

4. Study of decontamination and maintenance for vehicle manipulator of ITER blanket remote handling system;Fusion Engineering and Design;2020-07

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