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

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
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

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.