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The ARIES-AT advanced tokamak, Advanced technology fusion power plant

机译:ARIES-AT先进托卡马克,先进技术融合发电厂

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The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive and competitive fusion power in order to guide fusion R&D. The 1000-MWe ARIES-AT design has a major radius of 5.2 m, a minor radius of 1.3 m, a toroidal β of 9.2% (β_N = 5.4) and an on-axis field of 5.6 T. The plasma current is 13 MA and the current-drive power is 35 MW. The ARIES-AT design uses the same physics basis as ARIES-RS, a reversed-shear plasma. A distinct difference between ARIES-RS and ARIES-AT plasmas is the higher plasma elongation of ARIES-AT (κ_x = 2.2) which is the result of a "thinner" blanket leading to a large increase in plasma β to 9.2% (compared to 5% for ARIES-RS) with only a slightly higher β_N. ARIES-AT blanket is a simple, low-pressure design consisting of SiC composite boxes with a SiC insert for flow distribution that does not carry any structural load. The breeding coolant (Pb-17Li) enters the fusion core from the bottom, and cools the first wall while traveling in the poloidal direction to the top of the blanket module. The coolant then returns through the blanket channel at a low speed and is superheated to ~1100℃. As most of the fusion power is deposited directly into the breeding coolant, this method leads to a high coolant outlet temperature while keeping the temperature of the SiC structure as well as interface between SiC structure and Pb-17Li to about 1000℃. This blanket is well matched to an advanced Brayton power cycle, leading to an overall thermal efficiency of ~59%. The very low afterheat in SiC composites results in exceptional safety and waste disposal characteristics. All of the fusion core components qualify for shallow land burial under U.S. regulations (furthermore, ~90% of components qualify as Class-A waste, the lowest level). The ARIES-AT study shows that the combination of advanced tokamak modes and advanced technology leads to an attractive fusion power plant with excellent safety and environmental characteristics and with a cost of electricity (4.7 c/kWh), which is competitive with those projected for other sources of energy.
机译:开展ARIES-AT研究是为了评估高性能托卡马克等离子体及其在聚变电厂中的先进技术的潜力,并确定具有最高吸引力的物理和技术领域,以实现具有吸引力和竞争力的聚变能力,从而指导聚变研究与开发。 1000 MWe ARIES-AT设计的主半径为5.2 m,次半径为1.3 m,环形β为9.2%(β_N= 5.4),轴向磁场为5.6T。等离子体电流为13 MA电流驱动功率为35 MW。 ARIES-AT设计使用与反向剪切等离子体ARIES-RS相同的物理基础。 ARIES-RS和ARIES-AT血浆之间的显着区别是ARIES-AT的血浆伸长率更高(κ_x= 2.2),这是“薄”覆盖层导致血浆β值大幅增加至9.2%的结果。对于ARIES-RS为5%,而β_N则稍高。 ARIES-AT橡皮布是一种简单的低压设计,由SiC复合材料盒和SiC插入件组成,用于不承担任何结构载荷的流量分配。繁殖冷却剂(Pb-17Li)从底部进入聚变核,并在沿极向方向移动到橡皮布模块的顶部时冷却第一壁。然后,冷却剂低速通过橡皮布通道返回,并过热至〜1100℃。由于大部分聚变能直接沉积到繁殖冷却液中,因此该方法可导致较高的冷却液出口温度,同时将SiC结构以及SiC结构与Pb-17Li之间的界面保持在约1000℃。该毯子非常适合先进的布雷顿(Brayton)功率循环,从而使整体热效率达到〜59%。 SiC复合材料中极低的余热导致出色的安全性和废物处置特性。根据美国法规,所有融合核组件均符合浅埋土的条件(此外,约90%的组件属于A级废物,是最低级别)。 ARIES-AT研究表明,先进的托卡马克模式和先进技术相结合,可以形成具有吸引力的融合发电厂,该电厂具有出色的安全性和环境特性,并且电力成本(4.7 c / kWh),与其他电厂相比具有竞争力能量来源。

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