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Parameter study of L–H transition for plasma operation scenario development in JA DEMO. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2022.113369] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/14/2022]
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Zheng J, Qin J, Lu K, Xu M, Duan X, Xu G, Hu J, Gong X, Zang Q, Liu Z, Wang L, Ding R, Chen J, Li P, Xue L, Cai L, Song Y. Recent progress in Chinese fusion research based on superconducting tokamak configuration. Innovation (N Y) 2022; 3:100269. [PMID: 35815072 PMCID: PMC9256834 DOI: 10.1016/j.xinn.2022.100269] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/28/2021] [Accepted: 06/08/2022] [Indexed: 11/24/2022] Open
Abstract
Fusion energy is a promising source of clean energy, which could solve energy shortages and environmental pollution. Research into controlled fusion energy has been ongoing for over half a century. China has created a clear roadmap for magnetic confinement fusion development, where superconducting tokamaks will be used in commercial fusion reactors. The Experimental Advanced Superconducting Tokamak (EAST) is the world’s first fully superconducting tokamak with upper and lower divertors, which aims at long-pulse, steady-state, H-mode operation, and 101-s H-mode discharge had been achieved. In 2007, China joined the International Thermonuclear Experimental Reactor (ITER) and became one of its seven members. Thirteen procurement packages are undertaken by China, covering superconducting magnets, power supplies, plasma-facing components (PFCs), diagnostics, etc. To bridge the gap between the ITER and fusion demonstration power plants (DEMOs), China is planning to build the Chinese Fusion Engineering Testing Reactor (CFETR) to demonstrate related technologies and physics models. The engineering design of the CFETR was completed in 2020, and Comprehensive Research Facilities for Fusion Technology (CRAFT) are being constructed to explore the key technologies used in the CFETR. Fusion energy is a promising source of clean energy Tokamak is the most widely studied magnetic confinement fusion device China built the world’s first fully superconducting tokamak -EAST China is one of the seven members of the ITER project CFETR engineering design has been completed, and its R&D is ongoing
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Zheng J, Song Y, Liu F, Liu X, Lu K, Zhu L, Xu W, Shen G, Fang C, Li C, Li M, Liu H. Progress in engineering design of CFETR toroidal field superconducting magnet. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113063] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Hayashi T, Takechi M, Matsunaga G, Isayama A. In-bore laser welding tool for actively cooled divertor cassettes in JT-60SA. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113040] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Ortwein R, Świerblewski J, Hromádka J, Kovařík K, Havlíček J, Šesták D, Patel N, Yanovskiy V, Pánek R. Analytical solution of tokamak vibrations during axisymmetric plasma disruptions. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2021.112997] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Sugiyama S, Shinya K, Utoh H, Aiba N, Sakamoto Y. A study on ohmic plasma initiation for JA DEMO. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112779] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Shin-mura K, Tokuyoshi R, Tazoe H, Sasaki K. Temperature effect on lithium isotope separation by electrodialysis using La0.57Li0.29TiO3 electrolyte. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112577] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Brazing Tungsten/Tantalum/RAFM Steel Joint for DEMO by Fully Reduced Activation Brazing Alloy 48Ti-48Zr-4Be. METALS 2021. [DOI: 10.3390/met11091417] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
To create a DEMO reactor, it is necessary to develop high-quality technology to join tungsten with reduced-activation ferritic-martensitic (RAFM) steel (Rusfer, Eurofer, CLF-1, etc.). Difficulties arise in their direct connection due to the large difference in the coefficient of thermal expansion (CTE). To suppress the difference of CTE, intermediate interlayers are usually used, such as vanadium or tantalum, and brazing is a prospective technology to conduct the joining. The vast majority of works represent copper- or nickel-based brazing alloys, but their applicability is under significant discussion due to their activation properties. That is why, in this work, fully reduced activation 48Ti-48Zr-4Be wt.% brazing alloy was used. The following joint was made: Rusfer steel/48Ti-48Zr-4Be/Ta/48Ti-48Zr-4Be/W. The brazing was successfully carried out under a mode providing thermal heat treatment of Rusfer. Through EDS and EBSD analysis, the microstructure of the joint was determined. Shear strength of the as-joined composition was measured as 127 ± 20 MPa. The joint endured 200 thermocycles in the temperature range between 300–600 °C, but the fillet regions degraded.
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Sasaki K, Hiraka R, Takahashi H, Shin-mura K. Energy balance of lithium recovery by electrodialysis using La0.57Li0.29TiO3 electrolyte. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112500] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Effect of temperature distribution on tritium permeation rate to cooling water in JA DEMO condition. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112576] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Miyoshi Y, Hiwatari R, Someya Y, Tokunaga S, Homma Y, Asakura N, Sakamoto Y, Tobita K. Analysis of peak heat load on the blanket module for JA DEMO. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2019.111394] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Chikada T, Kimura K, Mochizuki J, Horikoshi S, Matsunaga M, Fujita H, Okitsu K, Tanaka T, Hishinuma Y, Sakamoto Y, Someya Y, Nakamura H. Surface oxidation effect on deuterium permeation in reduced activation ferritic/martensitic steel F82H for DEMO application. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.12.089] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Utoh H, Kakudate S, Hiwatari R, Someya Y, Sakamoto Y, Asakura N, Tokunaga S, Tobita K. Progress on reliability of remote maintenance concept for JA DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.133] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Hiwatari R, Katayama K, Nakamura M, Miyoshi Y, Aoki A, Asakura N, Utoh H, Homma Y, Tokunaga S, Nakajima N, Someya Y, Sakamoto Y, Tobita K. Development of plant concept related to tritium handling in the water-cooling system for JA DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.174] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Tobita K, Hiwatari R, Sakamoto Y, Someya Y, Asakura N, Utoh H, Miyoshi Y, Tokunaga S, Homma Y, Kakudate S, Nakajima N, for Fusion DEMO TJSDT. Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade. FUSION SCIENCE AND TECHNOLOGY 2019. [DOI: 10.1080/15361055.2019.1600931] [Citation(s) in RCA: 15] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Kenji Tobita
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Ryoji Hiwatari
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Yoshiteru Sakamoto
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Youji Someya
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Nobuyuki Asakura
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Hiroyasu Utoh
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Yuya Miyoshi
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Shinsuke Tokunaga
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Yuki Homma
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
| | - Satoshi Kakudate
- National Institutes for Quantum and Radiological Science and Technology, Rokkasho, Aomori 039-3212, Japan
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Nie B, Jiang M, Ni M, Li F. Preliminary environmental radiation considerations for CFETR. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.119] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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