Irradiation Tests of the Sleeve for the Telescopic Arm of the ITER Blanket Remote Handling System
Author:
Affiliation:
1. Naka Institute for Fusion Science and Technology, National Institutes for Quantum Science and Technology
Publisher
Japan Society of Plasma Science and Nuclear Fusion Research
Link
https://www.jstage.jst.go.jp/article/pfr/19/0/19_1405020/_pdf
Reference9 articles.
1. [1] Y. Noguchi, M. Saito, T. Maruyama and N. Takeda, Design Progress of ITER Blanket Remote Handling System towards Manufacturing, Fusion Eng. Des. 136, A, 722 (2018).
2. [2] G. Damiani et al., Overview of the ITER remote maintenance design and of the development activities in Europe, Fusion Eng. Des. 136, 1117 (2018).
3. [3] M. Saito, H. Kozaka, T. Maruyama, Y. Noguchi, K. Nakata, N. Takeda and S. Kakudate, Irradiation tests of radiation hard materials for ITER blanket remote handling system, Fusion Eng. Des. 124, 542 (2017).
4. [4] PEEK Biomaterials Handbook, 2012, Pages 75-79.
5. [5] M. Saito and N. Takeda, Decontamination tests of dust under load for the ITER Blanket Remote Handling System, Fusion Eng. Des. 146, part B, 2765 (2019).
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