Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment-Reference-Cited by-同舟云学术

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Published:2014-12 Issue:1-3 Volume:455 Page:277-291
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Stork D.,Agostini P.,Boutard J.L.,Buckthorpe D.,Diegele E.,Dudarev S.L.,English C.,Federici G.,Gilbert M.R.,Gonzalez S.,Ibarra A.,Linsmeier Ch.,Li Puma A.,Marbach G.,Morris P.F.,Packer L.W.,Raj B.,Rieth M.,Tran M.Q.,Ward D.J.,Zinkle S.J.

Publisher

Elsevier BV

Subject

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

Reference95 articles.

1. F. Romanelli, et al., Roadmap to the Realisation of Fusion Energy, Fusion Eng and Design, 2013 (Submitted for publication).

2. D. Stork et al., Assessment of the EU R&D Programme on DEMO Structural, Plasma Facing and High Heat flux Materials, CCEFu57-7.1, European Commission (2012).

3. P.J. Knight. A User’s Guide to the PROCESS Systems Code, UKAEA Fusion, 2.1.0. ed., July 1996.

4. G. Federici, R. Kemp, D.J. Ward, et al., Overview of EU DEMO Design and R&D Activities, Fusion Eng and Design, March 2014 (in press).

5. A.R. Loving, et al., Pre-conceptual Design Assessment of DEMO Remote Maintenance, in: 11th Intl Conf on Fusion Nuclear Technology (ISFNT-11), Barcelona, September 2013. Fusion Engineering and Design, October 2013 (Submitted for publication).

Cited by 216 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. Experimental electronic stopping cross-section of EUROFER97 for slow protons, deuterons and helium ions;Radiation Physics and Chemistry;2024-11

2. Validation activities at ENEA Brasimone in support of the IFMIF-DONES design;Journal of Nuclear Materials;2024-10

3. Fracture modes and grain growth of tungsten during extreme cyclic heating;Journal of Nuclear Materials;2024-10

4. The IFMIF-DONES Diagnostics and Control Systems: Current Design Status, Integration Issues and Future Perspectives Embedding Artificial Intelligence Tools;Journal of Fusion Energy;2024-06-10

5. Development of reduced-activation and radiation-resistant high-entropy alloys for fusion reactor;International Journal of Refractory Metals and Hard Materials;2024-06