EHF FW panel for ITER BM with mechanical attachment of the plasma-facing components-Reference-Cited by-同舟云学术

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EHF FW panel for ITER BM with mechanical attachment of the plasma-facing components

Published:2019-09 Issue: Volume:146 Page:2407-2411
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Tomilov S.,Sviridenko M.,Leshukov A.,Gervash A.,Okuneva E.,Mazul I.,Safronov V.,Calcagno B.,Eaton R.,Gicquel S.,Raffray R.

Publisher

Elsevier BV

Subject

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

Reference5 articles.

1. Overview of JSC “NIKIET” activity on ITER Procurement Arrangements;Leshukov;Fusion Eng. Des.,2016

2. The ITER blanket system design challenge;Raffray;Nucl. Fusion,2014

3. Analysis results of the EHF FW Panel with welded fingers;Sviridenko;Fusion Eng. Des.,2014

4. Detailed 3-D nuclear analysis of ITER blanket modules;Bohm;Fusion Eng. Des.,2014

5. ITER Structural Design Criteria for In-vessel Components (SDCIC);IO ITER,2012

Cited by 3 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. High heat flux components with beryllium armour: From the small-scale mock-ups to the full-scale prototype of the ITER first wall panel;Fusion Engineering and Design;2024-06

2. Oxidation protection of tungsten alloys for nuclear fusion applications: A comprehensive review;Journal of Alloys and Compounds;2021-12

3. Analysis of Enhanced Heat Flux First Wall behavior under ITER Pulsed Loads;Fusion Engineering and Design;2020-09

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