Fusion Nuclear Science Facility (FNSF)

Y-K.M. Peng, J.M. Park, J. Canik, S. Diem, A. Sontag, A. Lumsdaine, Yl Katoh, R. Burgess, K. Korsah, B. Patton, J. Wagner, P. Fogarty, M. Sawan
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引用次数: 3

Abstract

A compact (R0∼1.2–1.3m), low aspect ratio, low-Q (<3) Fusion Nuclear Science Facility (FNSF) was recently assessed to provide a fully integrated, D-T-fueled, continuously driven plasma, volumetric nuclear environment of copious neutrons. This environment would be used, for the first time, to carry out discovery-driven research in fusion nuclear science and materials, in parallel with and complementary to ITER. This research would aim to test, discover, and understand new nuclear-nonnuclear synergistic interactions involving plasma material interactions, neutron material interactions, tritium fuel breeding and transport, and power extraction, and innovate and develop solutions for DEMO components. This facility properly designed could provide, initially using conservative JET-level D-T plasmas in Hot-Ion H-Mode, and an outboard fusion neutron flux of ∼0.33 MW/m2. If the research, facility operation, and component solutions were successful, the performance could be raised to 1 MW/m2 (fusion power ∼76 MW) by reaching for twice the JET plasma pressure and Q. Stable high-safety factor q and ² plasmas would be chosen to minimize plasma-induced disruptions, and deliver reliably a neutron fluence of 1 MW-yr/m2, if duty factors of ∼10% (accumulated plasma burn time in a year) can be achieved. Such duty factors would therefore require time-efficient installation and replacement of all components using remote handling (RH). These in turn would require RH-compatible modular designs for all internal components, a single-turn toroidal field coil center-post, and placement of support structures and vacuum seal welds behind the internal and shielding components. RH-enabled hot-cell laboratories would enable preparation and investigations of damages of the internal test components. The scientific and technical basis for such an FNSF, and the research needed in the next decade to manage the potential risks in its research capabilities, will be described.
聚变核科学设施(FNSF)
一个紧凑的(R0 ~ 1.2-1.3m),低纵横比,低q(<3)聚变核科学设施(FNSF)最近被评估为提供一个完全集成的,d - t燃料,连续驱动等离子体,大量中子的体积核环境。这种环境将首次用于开展核聚变科学和材料方面的发现驱动型研究,与ITER并行并互为补充。本研究旨在测试、发现和理解新的核-非核协同相互作用,包括等离子体材料相互作用、中子材料相互作用、氚燃料增殖和运输以及电力提取,并为DEMO组件创新和开发解决方案。如果设计得当,该设施可以在热离子h模式下使用保守的喷射级D-T等离子体,并提供约0.33 MW/m2的外部聚变中子通量。如果研究、设施运行和组件解决方案成功,通过达到JET等离子体压力和q的两倍,性能可以提高到1 MW/m2(聚变功率~ 76 MW),稳定的高安全系数q和²等离子体将被选择以最大限度地减少等离子体引起的中断,并可靠地提供1 MW-yr/m2的中子通量,如果占空因子为~ 10%(一年累积的等离子体燃烧时间)可以实现。因此,这种负载因素需要使用远程处理(RH)高效地安装和更换所有组件。这反过来又需要对所有内部组件进行rh兼容的模块化设计,单匝环形磁场线圈中心柱,并在内部和屏蔽组件后面放置支撑结构和真空密封焊缝。启用rh的热电池实验室将能够对内部测试组件的损坏进行准备和调查。本文将描述建立这样一个国家科学基金会的科学和技术基础,以及未来十年为管理其研究能力中的潜在风险所需要的研究。
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