Engineering Validation and Engineering Design of Lithium Target Facility in IFMIF/EVEDA Project-Reference-Cited by-同舟云学术

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Engineering Validation and Engineering Design of Lithium Target Facility in IFMIF/EVEDA Project

Published:2014-08 Issue:1 Volume:66 Page:46-56
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Wakai E.¹,Kondo H.¹,Kanemura T.¹,Furukawa T.¹,Hirakawa Y.¹,Watanabe K.¹,Ida M.¹,Ito Y.¹,Niitsuma S.¹,Edao Y.¹,Fujishiro K.¹,Nakaniwa K.¹,Hoashi E.²,Horiike H.²,Serizawa H.²,Kawahito Y.²,Fukada S.³,Sugie Y.³,Suzuki A.⁴,Yagi J.⁵,Tsuji Y.⁶,Furuya K.⁷,Groeschel F.⁸,KNASTER J.⁸,MICCHICHE G.⁹,IBARRA A.¹⁰,HEIDINGER R.¹¹,NITTI F.⁸⁹,SUGIMOTO M.¹²

Affiliation:

1. Japan Atomic Energy Agency, Ibaraki 319-1195, Japan

2. Osaka University, Osaka, Japan

3. Kyushu University, Fukuoka, Japan

4. University of Tokyo, Ibaraki, Japan

5. National Institute for Fusion Science, Gifu, Japan

6. Nagoya University, Aichi, Japan

7. College of Hachinohe, Aomori, Japan

8. Project Team of IFMIF/EVEDA Project, Aomori, Japan

9. ENEA, Brasimone, Italy

10. Ciemat, Madrid, Spain

11. Fusion for Energy, Garching, Germany

12. Japan Atomic Energy Agency, Aomori, Japan

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST13-770

Reference33 articles.

1. Effect of helium production on swelling of F82H irradiated in HFIR

2. Tensile properties and damage microstructures in ORR/HFIR-irradiated austenitic stainless steels

3. Swelling of cold-worked austenitic stainless steels irradiated in HFIR under spectrally tailored conditions

4. Effect of triple ion beams in ferritic/martensitic steel on swelling behavior

5. Microstructural study of irradiated isotopically tailored F82H steel

Cited by 5 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 design and thermo-structural analysis of target assembly for high intensity neutron source;Nuclear Materials and Energy;2018-12

2. The IFMIF-DONES project: preliminary engineering design;Nuclear Fusion;2018-08-30

3. Engineering validation for lithium target facility of the IFMIF under IFMIF/EVEDA project;Nuclear Materials and Energy;2016-12

4. Nitrogen Hot Trap Design and Manufactures for Lithium Test Loop in IFMIF/EVEDA Project;Plasma and Fusion Research;2016

5. The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source;Nuclear Fusion;2015-07-22

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