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

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

日渡 良爾

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌ATOMOΣ (ISSN:18822606)

巻号頁・発行日

vol.60, no.8, pp.488-492, 2018 (Released:2020-04-02)

参考文献数

17

被引用文献数

1 1

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本稿では,核融合炉のトリチウム燃料循環システムにおけるトリチウムバランスの基本的な考え方とモデル化について概説する。また原型炉における評価例を紹介し,トリチウムインベントリの挙動,必要となる初期装荷トリチウム量,トリチウム倍増時間について説明する。その後,原型炉に向けた課題としてトリチウムバランスのモデル化に必要なトリチウム損失係数の重要性,原型炉のトリチウムインベントリ最小化に向けた燃料システム構成の提案例について紹介する。

著者

高木 雅昭 岩船 由美子 山本 博巳 山地 憲治 岡野 邦彦 日渡 良爾 池谷 知彦

出版者

一般社団法人 電気学会

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.7, pp.651-660, 2010-07-01

参考文献数

19

被引用文献数

3 1

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In the power sector, the national government has set the goal that the introduction of PV reaches 53 million kW by 2030. However, large-scale introduction of PV will cause several problems in power systems such as surplus electricity. We need large capacity of pumped storages or batteries for the surplus electricity, but the construction costs of these plants are very high. On the other hand, in the transport sector, Electric Vehicle (EV) is being developed as an environmentally friendly vehicle. To promote the diffusion of EV, it is necessary to build infrastructures that can charge EV in a short time; a battery switch station is one of the solutions to this problem. At a station, the automated switch platform will replace the depleted battery with a fully-charged battery. The depleted battery is placed in a storage room and recharged to be available to other drivers. In this study, we propose the use of station's battery as a countermeasure for surplus electricity of PV and evaluate the economic value of the proposed system. We assumed that 53 million kW of PV is introduced in the nationwide power system and considered two countermeasures for surplus electricity: (1) Pumped storage; (2) Battery of station. The difference in total annual cost between Pumped case and Battery case results in 792.6 billion yen. Hence, if a utility leases the batteries from stations fewer than 792.6 billion yen, the utility will have the cost advantage in Battery case.

著者

日渡 良爾

出版者

一般財団法人電力中央研究所

雑誌

若手研究(B)

巻号頁・発行日

2011

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核融合エネルギーでは水素の同位体である重水素とトリチウムを燃料に利用する.自然界に存在しない燃料(トリチウム)を利用するため,核融合エネルギー開発の課題の一つに初期装荷用トリチウム燃料の入手が挙げられている.ここでは,重水素による僅かな核融合反応を利用しトリチウムを徐々に増殖し,定格運転までの出力に到達するという初期装荷用のトリチウム燃料を必要としない炉心プラズマ運転方法について詳細化し,プラズマの立ち上げ期間をできるだけ短くするといった観点から炉概念の最適化に向けた検討を行うことにより,初期装荷用トリチウム燃料の入手課題解決に貢献する.

著者

日渡 良爾 岡野 邦彦 朝岡 善幸 時松 宏治 小西 哲之 小川 雄一

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.903-916, 2005-11-25

被引用文献数

1 3

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The present study reveals forthcoming break-even conditions of tokamak plasma performance for the fusion energy development. The first condition is the electric break-even condition, which means that the gross electric power generation is equal to the circulating power in a power plant. This is required for fusion energy to be recognized as a suitable candidate for an alternative energy source. As for the plasma performance (normalized beta value β_N, confinement improvement factor for H-mode HH, the ratio of plasma density to Greenwald density fn_<GW>), the electric break-even condition requires the simultaneous achievement of 1.2<β_N<2.7, 0.8<HH, and 0.3<fn_<GW><1.1 under the conditions of a maximum magnetic field on the TF coil B_<max>=16 T, thermal efficiency η_e=30%, and current drive power P_<NBI><200 MW. It should be noted that the relatively moderate conditions of β_N〜1.8, HH〜1.0, and/fn_<GW>〜0.9, which correspond to the ITER reference operation parameters, have a strong potential to achieve the electric break-even condition. The second condition is the economic break-even condition, which is required for fusion energy to be selected as an alternative energy source in the energy market. By using a long-term world energy scenario, a break-even price for introduction of fusion energy in the year 2050 is estimated to lie between 65 mill/kWh and 135 mill/kWh under the constraint of 550 ppm CO_2 concentration in the atmosphere. In the present study, this break-even price is applied to the economic break-even condition. However, because this break-even price is based on the present energy scenario including uncertainties, the economic break-even condition discussed here should not be considered the sufficient condition, but a necessary condition. Under the conditions of β_<tmax>=16 T, η_e=40%, plant availability 60%, and a radial build with/without CS coil, the economic break-even condition requires β_N〜5.0 for 65 mill/kWh of lower break-even price case. Finally, the present study reveals that the demonstration of steady-state operation with β_N〜3.0 in the ITER project leads to the upper region of the break-even price in the present world energy scenario, which implies that it is necessary to improve the plasma performance beyond that of the ITER advanced plasma operation.

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

朝岡 善幸 日渡 良爾 岡野 邦彦

出版者

電力中央研究所

雑誌

電力中央研究所報告 T 研究報告

巻号頁・発行日

no.3008, pp.1-20,巻頭1〜5, 2004-01

著者

日渡 良爾 岡野 邦彦 朝岡 善幸 小川 雄一

雑誌

電気学会研究会資料. NE, 原子力研究会

巻号頁・発行日

vol.2006, no.1, pp.1-6, 2006-09-08

著者

朝岡 善幸 日渡 良爾 岡野 邦彦 伊勢 英夫 野本 恭信

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会年会予稿集

巻号頁・発行日

no.20, 2003-11-18

著者

岡野 邦彦 朝岡 善幸 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.80, no.3, pp.241-248, 2004-03-25

被引用文献数

1

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Beam driven stable equilibria for a conceptual reactor, Demo-CREST, which was designed for early demonstration of electric power generation, has been investigated. Considering current profiles driven by neutral beams, the attainable normalized beta β_N with a stabilization wall is about 3.4 with a normal shear (NS). With reversed shear (RS), a higher β_N is attainable. The stable equilibria up to 4.0 can be sustained by a couple of On-and Off-axis beams. In the range of 1.9<β_N<4.0, power of each beam does not exceed the power in the case of β_N=1.9 which is the base design point of Demo-CREST. In the case of RS operation with β_N=4.0, the density ratio to the Greenwald limit can be maintain at about unity if high temperature operation with T_e>20keV is allowable.