Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO
Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO
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1.5 GW级聚变发电DEMO的功率排放和偏滤器设计研究
DOI：
10.1088/1741-4326/aa867a
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发表时间：
2017
期刊：
影响因子：
3.3
通讯作者：
Joint Special Team for Demo Design
中科院分区：
文献类型：
--
作者：
N. Asakura;K. Hoshino;S. Suzuki;S. Tokunaga;Y. Someya;H. Utoh;Hironobu Kudo;Y. Sakamoto;R. Hiwatari;K. Tobita;K. Shimizu;K. Ezato;Y. Seki;N. Ohno;Y. Ueda;Joint Special Team for Demo Design
在日本的一个具有1.5 gw级聚变功率、主半径为8.5 m的稳态DEMO中，对引流器的功率排放和概念设计进行了研究，并对等离子体参数进行了修改，以适应杂质播种的情况。对Ar杂质播撒的系统代码调查表明，psp主等离子体的体积平均密度、杂质浓度和排气功率为205 ~ 285 MW。在引流器支腿长度为1.6 m的条件下，进行了引流器等离子体模拟（SONIC），设定引流器边缘排气功率为250 MW，边缘总辐射分数、SOL和引流器（Prad/Pout = 0.8），作为研究适当设计引流器尺寸和几何形状的第一步。在外靶处，在撞击点附近产生部分分离，在适当的燃料和杂质吞吐率下，附着区域的峰值热负荷（qtarget）降至~5 MW m−2。在内导流器靶处，离子通量完全脱离，峰值qtarget小于10 MW m−2，这主要是由于表面复合所致。这些结果展示了一个动力排气场景和导流器的设计概念。提出了一种长腿导流器水冷散热器的一体化设计方案。Cu-ally （CuCrZr）冷却管作为散热器适用于处理冲击点附近的高热流密度，其中每个原子的位移率估计为每年0.5-1.5。研究了cu -合金和还原活化铁素体马氏体（RAFM）钢（F82H）管在导流箱内的冷却剂根部布置，并对w -单块和cu -合金管在10 mw−2的峰值目标和核加热下的传热进行了分析。w表面和cu合金管的最高温度分别为1021℃和331℃。热流密度为16 MW m−2，分布在冷却剂管道的主体部分。这些结果对于等离子体表面和结构材料是可以接受的。
Power exhaust to the divertor and the conceptual design have been investigated for a steady-state DEMO in Japan with 1.5 GW-level fusion power and the major radius of 8.5 m, where the plasma parameters were revised appropriate for the impurity seeding scenario. A system code survey for the Ar impurity seeding suggested the volume-averaged density, impurity concentration and exhaust power from the main plasma of Psep = 205–285 MW. The divertor plasma simulation (SONIC) was performed in the divertor leg length of 1.6 m with the fixed exhaust power to the edge of Pout = 250 MW and the total radiation fraction at the edge, SOL and divertor (Prad/Pout = 0.8), as a first step to investigate appropriate design of the divertor size and geometry. At the outer target, partial detachment was produced near the strike-point, and the peak heat load (qtarget) at the attached region was reduced to ~5 MW m−2 with appropriate fuel and impurity puff rates. At the inner divertor target, full detachment of ion flux was produced and the peak qtarget was less than 10 MW m−2 mostly due to the surface-recombination. These results showed a power exhaust scenario and the divertor design concept. An integrated design of the water-cooling heat sink for the long leg divertor was proposed. Cu-ally (CuCrZr) cooling pipe was applicable as the heat sink to handle the high heat flux near the strike-point, where displacements per atom rate was estimated to be 0.5–1.5 per year by neutronics calculation. An arrangement of the coolant rooting for Cu-alloy and Reduced Activation Ferritic Martensitic (RAFM) steel (F82H) pipes in a divertor cassette was investigated, and the heat transport analysis of the W-monoblock and Cu-alloy pipe under the peak qtarget of 10 MWm−2 and nuclear heating was performed. The maximum temperatures on the W-surface and Cu-alloy pipe were 1021 and 331 °C. Heat flux of 16 MW m−2 was distributed in the major part of the coolant pipe. These results were acceptable for the plasma facing and structural materials.