Conceptual design of Japan’s fusion DEMO reactor (JA DEMO) and superconducting coil issues
Conceptual design of Japan’s fusion DEMO reactor (JA DEMO) and superconducting coil issues
复制标题
日本聚变DEMO反应堆（JA DEMO）概念设计和超导线圈问题
DOI：
10.1088/1742-6596/1293/1/012078
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发表时间：
2019
期刊：
影响因子：
--
通讯作者：
The Joint Special Design Team for Fusion DEMO
中科院分区：
文献类型：
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作者：
Tobita K.;Utoh H.;Hiwatari R.;Miyoshi Y.;Tokunaga S.;Sakamoto Y.;Someya Y.;Asakura N.;Homma Y.;Nakajima N.;The Joint Special Design Team for Fusion DEMO
日本的聚变示范（DEMO）反应堆的目标是证明（1）在发电厂规模下稳定和稳定的发电，（2）自给自足的燃料（氚）生产，以及（3）使用商业工厂预期的远程维护计划的合理可用性。JA DEMO的主要设计参数是等离子体半径8.5 m，聚变输出1.5-2 GW，等离子体轴上的磁场5.94 T。该反应堆的超导线圈系统由一个中心螺线管（CS）、7个极向场（PF）线圈和16个环向场（TF）线圈组成。关于CS和PF线圈，DEMO上的超导线圈技术与世界上最大的聚变实验堆ITER上的超导线圈技术基本相同。相比之下，TF线圈由于其尺寸和磁场而在磁能和ITER与DEMO之间产生的应力方面存在技术差距。特别是，更高的设计应力的必要性对于TF线圈是至关重要的，需要开发超过现有的高强度低温钢。最后提出了减小TF线圈制造公差的基本设计策略。
Goals of Japan's fusion demonstration (DEMO) reactor are to demonstrate (1) steady and stable electric power generation in a power plant scale,(2) self-sufficient production of fuel (tritium), and (3) reasonable availability using a remote maintenance scheme anticipated in a commercial plant. Main design parameters of JA DEMO are a plasma major radius of 8.5 m, fusion output of 1.5-2 GW, magnetic field on the plasma axis of 5.94 T. The superconducting coil system of the reactor consists of a central solenoid (CS), 7 poloidal field (PF) coils and 16 toroidal field (TF) coils. Regarding CS and PF coils, superconducting coil technology on DEMO is basically the same as that on the world largest fusion experimental reactor called ITER. In contrast, TF coils have a technology gap on magnetic energy and the resulting stress between ITER and DEMO due to their size and magnetic field. In particular, the necessity of higher design stress is critical for TF coils, requiring the development of high strength cryogenic steels surpassing the existing ones. The fundamental design strategy to mitigate tolerances in TF coil fabrication is also presented.