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OVERVIEW OF RECENT JAPANESE ACTIVITIES AND PLANS IN FUSION TECHNOLOGY

机译:融合技术中的近期日本活动和计划概述

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For ITER, trial fabrications of a superconducting cable for a Toroidal Field coil conductor and jacket sections for a central solenoid conductor were successfully performed. In the radio-frequency heating technology, development of 170 GHz ITER gyrotron has progressed to achieve a 600 kW for 3600 sec operation in JAEA RF test stand. In LHD, long-pulse operations near 1 hour with 1.6 GJ inputs have been achieved with ICH and ECH, and subcooled operations of SC magnets to improve cryogenic stability are scheduled soon. In the ITER Test Blanket Modules project, Japan has a plan to lead a water cooled ceramic breeder blanket concept, and to cooperate with other parties on other blanket concepts, such as, a helium cooled ceramic breeder blanket, a LiPb blanket, a Li/V blanket, and a molten salt blanket. As the Broader Approach activities between Europe and Japan, ITER satellite tokamak, JT-60SA, IFMIF-EVEDA and the International Fusion Energy Research Center programs will start soon in Naka and Rokkasho, respectively. Basic researches on broad areas have been enhanced with collaborations in the Fusion Engineering Network among Japanese universities and research institutes.
机译:对于ITER,成功完成了环形场线圈导体的超导电缆和中央螺线管导体的护套部分的试制。在射频加热技术中,开发了170 GHz ITER陀螺仪,在JAEA RF测试台上可实现3600 sec的运行功率达到600 kW。在LHD中,使用ICH和ECH可以在1.6 GJ输入下实现近1小时的长脉冲运行,并计划很快进行SC磁体的过冷运行以提高低温稳定性。在ITER测试毯模块项目中,日本计划领导水冷陶瓷育种毯概念,并与其他方就其他毯概念进行合作,例如氦冷却陶瓷育种毯,LiPb毯,Li / V毯和一条融盐毯。随着欧洲和日本之间的“更广泛方法”活动的开展,ITER卫星托卡马克,JT-60SA,IFMIF-EVEDA和国际聚变能源研究中心计划将分别在纳卡和六所町开始。通过日本大学和研究机构之间融合工程网络的合作,扩大了广泛领域的基础研究。

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