著者

魏 啓為 佐野 史典 秋元 圭吾 日渡 良爾 飛田 健次

出版者

一般社団法人 エネルギー・資源学会

雑誌

エネルギー・資源学会論文誌 (ISSN:24330531)

巻号頁・発行日

vol.40, no.5, pp.170-179, 2019 (Released:2019-09-10)

参考文献数

20

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This paper analyzed Japan’s fusion energy development scenarios by using a global energy systems model considering a combination of uncertainties of future socioeconomic development, CO2 emission pathways corresponding to the long-term target of the Paris Agreement and future fusion power plants. Fusion power plants will be installed in Japan and could contribute about 20% on average in power sector in the latter half of the century because of the limited-potentials of affordable renewable energies and carbon capture and storage in Japan. The benefit of fusion introduction in Japan is estimated to be about 10 billion US$/yr on average in 2050-2100. Its value increases with reduction of the capital costs of future fusion power plants, lower penetration of fission power plants and deeper decarbonization pathways. When considering unique characteristics of fusion energy development, i.e., long-term and large-scale projects and DEMO as a single step between ITER and a first commercial plant, demonstration and prospect of economic viability under DEMO projects becomes critically important. This systems analysis also suggests that an alternative option of fusion energy which directly produces hydrogen by high-temperature steam electrolysis could become economically attractive.

著者

岡野 邦彦 小川 雄一 飛田 健次

出版者

The Institute of Electrical Engineers of Japan

雑誌

電気学会論文誌. B, 電力・エネルギー部門誌 = The transactions of the Institute of Electrical Engineers of Japan. B, A publication of Power and Energy Society (ISSN:03854213)

巻号頁・発行日

vol.130, no.4, pp.395-398, 2010-04-01

参考文献数

7

被引用文献数

2

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This paper describes a prospect toward electric power production by the Fusion energy. In the first part of the paper, a principle of TOKAMAK system which is the successful magnetic-confinement-systems for fusion reactors are shown, and then the ITER project based on TOKAMAK and the present status of ITER is reviewed. In the remainder of the paper, a roadmap for fusion energy and conceptual designs of Demonstration reactors are briefly described.

著者

飛田 健次 日渡 良爾

出版者

社団法人 プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.78, no.11, pp.1179-1185, 2002 (Released:2005-12-08)

参考文献数

19

被引用文献数

3 2

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Waste management at fusion power plants is reviewed. Recent study indicates that most of the waste from a fusion reactor can be cleared from regulatory control over a 50-year cooling after decommissioning. In addition, the remaining metal radioactive waste is anticipated to be recyclable within 100-year cooling. These results indicate the prospect of a low emission system of fusion energy materials.

著者

飛田 健次

出版者

一般社団法人 電気学会

雑誌

電気学会誌 (ISSN:13405551)

巻号頁・発行日

vol.128, no.2, pp.86-89, 2008-02-01 (Released:2008-02-01)

参考文献数

4

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本記事に「抄録」はありません。

著者

武智 学 松永 剛 白石 淳也 徳田 伸二 飛田 健次

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.85, no.4, pp.147-162, 2009-04-25

被引用文献数

1

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トカマク型核融合炉の定常化にとって高ベータ化は必須である.この高ベータ化には最終的にはMHD不安定性の一種である"抵抗性壁モード"がボスキャラのごとく立ちはだかる.逆転磁場ピンチに至っては抵抗性壁モードによって寿命が決まってしまう.この十年,閉じ込め改善や加熱装置の進展により高ベータ化の敵,抵抗性壁モードとの実戦が始まった.この敵を駆逐する(安定化する)武器には"プラズマ回転"と"磁場のフィードバック制御"があるが,最近その戦いにちょっとしたどんでん返しがあった.その結構ドラマチックな戦歴を楽しんでもらうために,まずは敵を知ってもらい,これらの武器の説明をしよう.その領域は物理から工学までの広い分野にわたる.現在の戦況は混沌としているが,さらに,問題点や今後の戦い方について考える.さあ,抵抗性壁モードの世界へ,ようこそ.

著者

飛田 健次

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.73, no.11, 1997-11-25

著者

飛田 健次 濱松 清隆 滝塚 知典 鈴木 正信

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.75, no.5, pp.582-593, 1999-05-25

被引用文献数

5 6

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Ripple loss of energetic alpha particles and neutral beam ions was calculated for reversed shear discharges in ITER-FDR(Final Design Report). The result indicates that, compared with normal operation with positive shear, reversed shear operation dramatically enhances the ripple loss. Ripple loss of alpha particles can reach 25% with the maximum heat load of 3.7MW/m^2 on the outboard wall, while that of a 1MeV negative ion source beam can be as high as 20% as well. The heat load due to alpha particle loss is marginal in the light of a wall tolerance. The calculation suggests that the Toroidal Field(TF)ripple in a fusion reactor should be designed to be less than 0.6% at the plasma surface so that ripple loss of alpha particles or beam ions can be acceptably low. Ferritic steel insert to the vacuum vessel, is a probable solution to reduce the ripple loss to an allowable level in the ITER-FDR design with the TF ripple reduction of by a factor of 0.4. With TF ripple reduction, ripple loss for alpha particles and beam ions is expected to decrease to 10% and 4%, respectively.

著者

西尾 敏 飛田 健次 牛草 健吉 小西 哲之 動力炉設計チーム 動力炉設計チーム

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会年会予稿集

巻号頁・発行日

no.18, 2001-11-20

著者

飛田 健次 小西 哲之 時松 宏治 西尾 敏 日渡 良爾

出版者

社団法人 プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.81, no.11, pp.875-891, 2005 (Released:2007-01-12)

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This section describes the future of fusion energy in terms of its impact on the global energy supply and global warming mitigation, the possible entry scenarios of fusion into future energy market, and innovative technologies for deploying and expanding fusion's share in the market. Section 5.1 shows that fusion energy can contribute to the stabilization of atmospheric CO2 concentration if fusion is introduced into the future energy market at a competitive price. Considerations regarding fusion's entry scenarios into the energy market are presented in Sec. 5.2, suggesting that fusion should replace fossil energy sources and thus contribute to global warming mitigation. In this sense, first generation fusion power plants should be a viable energy source with global appeal and be so attractive as to be employed in developing countries rather than in developed countries. Favorable factors lending to this purpose are fusion's stability as a power source, and its security, safety, and environmental frendliness as well as its cost-of-electricity. The requirements for core plasma to expand the share of fusion in the market in the latter half of this century are given in Sec.5.3, pointing out the importance of high beta access with low aspect ratio and plasma profile control. From this same point of view, innovative fusion technologies worthy of further development are commented on in Sec. 5.4, addressing the high temperature blanket, hydrogen production, high temperature superconductors, and hot cell maintenance.

著者

飛田 健次 小西 哲之 西尾 敏 小迫 和明 田原 隆志

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.77, no.10, pp.1035-1039, 2001-10-25

被引用文献数

4

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A new concept of fusion reactor design is proposed to minimize the radioactive waste of the reactor. The main point of the concept is to clear massive structural components located outside the neutron shield from regulatory control. The concept requires some reinforcement of shielding with an advanced shield material such as a metal hydride, detriation, and tailoring of a detrimental element from the superconductor. Our assessment confirmed a large impact of the concept on radwaste reduction, in that it reduces the radwaste fraction of a fusion reactor A-SSTR2 from 92wt.% to 17wt.%.

著者

谷 啓二 飛田 健次 西尾 敏 飯尾 俊二 筒井 広明 青木 尊之

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.80, no.11, pp.931-934, 2004-11-25

被引用文献数

1 1

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Studies were made on ripple losses of fusion produced alpha particles in a low-aspect-ratio tokamak reactor (VECTOR) by using an orbit-following Monte-Carlo code. Alpha particles are well confined in VECTOR. In a low-aspect-ratio tokamak, the dependence of ripple losses on the number of toroidal-field (TF) coils N is very weak. Assuming a toroidal peaking factor of 2 for the heat load due to loss particles, about 1.5% and 1.0% of TF ripple at the outer edge of plasma might be allowable for the first wall with and without cooling system, respectively. In both cases, the number of TF-coils can be reduced to about 4.