Materials design and related R&D issues for the force-free helical reactor (FFHR)-Reference-Cited by-同舟云学术

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Materials design and related R&D issues for the force-free helical reactor (FFHR)

Published:1998-10 Issue: Volume:258-263 Page:2079-2082
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sagara A,Muroga T,Motojima O,Noda T,Tanaka S,Terai T,Kohyama A,Matsui H

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. A. Sagara et al., Fusion Eng. Design 29 (1995) 51

2. K. Yamazaki, A. Sagara et al., Sixteenth IAEA Fusion Energy Conference 1996, Montreal, IAEA-CN-64/G1-5

3. A. Sagara et al, Proceedings of ISFNT-4, Fusion Engrg. Design., in press

4. A. Iiyoshi et al., Fusion Technol. 17 (1990) 169

5. O. Motojima et al., in: Plasma Physics and Cont. Nucl. Fusion Research 1990, Washington, IAEA-CN-53/G-1-5

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1. Rejuvenation of spent fuel in the force-free helical reactor (FFHR);Annals of Nuclear Energy;2005-03

2. Study of fissile fuel breeding concept for the force-free helical reactor;Fusion Engineering and Design;2003-07

3. Compatibility of structural candidate materials with LiF–BeF2 molten salt mixture;Journal of Nuclear Materials;2000-12

4. Tritium Loss in Molten Flibe Systems;Fusion Technology;2000-11

5. Correlation of Hardening and Microstructure of Tantalum Irradiated with Heavy Ions;Effects of Radiation on Materials: 19th International Symposium

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