逆磁場ピンチ型核融合炉の基本パラメータ

概要

論文の詳細を見る
A quantitative estimation has been made to survey the possibility of whether a reversed field pinch(RFP) can be a simple fusion reactor. Since the DT reaction rate divided by the square of the temperature becomes a weak temperature function (within ± 15% variation) in the range between 10 keV and 30 keV, several simple relations can be derived between basic parameters of the reactor in the DT burning condition. For example, the value of plasma current (I_p) is almost determined by the values of poloidal beta (β_p) and effective thermal diffusibility (x_<xlb>=a^2/τ_E, a;minor radius, τ_E;global energy confinement time), which is independent of other basic reactor parameters such as major radius (R), minor radius, total fusion output (W_f), and neutron wall loading (Γ_n). By using these relations, necessary conditions in confinement properties, such as β_p and x_<glb>are surveyed for obtaining the realistic values of basic reactor parameters in RFP. Results show that if the β_p of about 0.2 and x_<glb> of about 2.2 m^2/s are realized, then the reasonable RFP reactor concept employing a normal conducting toroidal coil system can be designed, where the values of W_f, Γ_n, R, a and I_p are 3 GW, 3 MW/m^2, 13 m, 1.5 m, and 25 MA, respectively. The joule loss of the toroidal coil, the flux swing for the setting up I_p and the maximum magnetic field for the flux swing in the central solenoid poloidal coil are estimated to be 80 MW, 2, 000 Vs, and ± 4T, respectively.
社団法人プラズマ・核融合学会の論文
2001-08-25

逆磁場ピンチ型核融合炉の基本パラメータ

スポンサーリンク

概要

著者

関連論文

スポンサーリンク