Deuterium-Tritium Levitated Dipole Fusion Power Plants
OpenStar Technologies Limited（OpenStar科技有限公司）
T. Simpson, R. A. Badcock, T. Berry, C. S. Chisholm, P. J. Fimognari, P. Fisher, D. T. Garnier, K. Lenagh-Glue, B. Leuw, R. Mataira, L. Meadows, T. McIntosh, J.… 展开作者
T. Simpson, R. A. Badcock, T. Berry, C. S. Chisholm, P. J. Fimognari, P. Fisher, D. T. Garnier, K. Lenagh-Glue, B. Leuw, R. Mataira, L. Meadows, T. McIntosh, J. Poata, K. Richardson, B. Smith, A. Simpson, J. D. Tyler, T. Wordsworth
备注：
31 pages, 23 figures, Submitted to Fusion Engineering and Design
Levitated dipole reactors offer an attractive path towards economic fusion power generation. The intrinsic decoupling of the confining magnetic field-generating REBCO magnets and the vacuum vessel offer unparalleled accessibility and maintainability, allowing for high plant duty factors and theoretically low electricity prices. In order to achieve rapid deployment of fusion power to the grid, the use of the Deuterium-Tritium (DT) fuel cycle is required due to its lower required plasma triple products. Historically, designs of levitated dipole fusion power plants have targeted advanced fuels as a DT device was seen to be infeasible due to the high fluxes of 14.1 MeV neutrons on the superconducting core magnet. This study presents high level designs for two feasible first-of-a-kind (FOAK) DT levitated dipole fusion power plants, the larger of which produces 667 MW of fusion power and is predicted to produce 208 MW of net electric power. Both designs consist of a heavily neutron-shielded, high-field REBCO core magnet capable of producing peak magnetic field strengths of 23 T while keeping peak mechanical strains below 0.4%. The neutron shielding is comprised of a layered structure of tungsten and boron carbide, which allows for 92% of the heat deposited in the neutron shield to be radiated out to the first wall while still providing sufficient neutron attenuation to give adequate REBCO conductor lifetimes. The core magnet REBCO coil is comprised of a small "sacrificial" section and a larger semi-permanent section. The sacrificial section, comprising ~20% of the coil, will have a neutron damage limited lifetime of ~1 year, after which the core magnet will be quickly removed from the vacuum vessel and replaced. This allows the damaged core magnet to be refurbished and reused, reducing cost and allowing for economic fusion power generation from a DT levitated dipole reactor.
Comment on "Deuterium--tritium fusion reactors without external fusion breeding" by Eliezer et al
Eliezer等人考虑的极端条件下氘-氘燃烧计算中包含逆康普顿效应[Phys. Lett. A 243（1998）298]所示的最大燃烧温度从约300 keV降低到仅100- 150 keV。这种减少使得通过DD -> T + p反应的氚增殖不足以取代最初添加到氘等离子体中以在小于10 keV下触发点火的少量氚。
Beam filamentation instability drives deuterium-tritium fusion with polarized neutron emission
State Key Laboratory of Nuclear Physics and Technology, Peking University（北京大学核物理与技术国家重点实验室）；Institute of Theoretical Physics, Chinese Academy of Sciences（中国科学院理论物理研究所）；College of Physics, Sichuan University（四川大学物理学院）；Beijing Laser Acceleration Innovation Center（北京激光聚变创新中心）
Neutron-source fidelity for laser-driven D--D lithium-blanket tritium-breeding tests
Key Laboratory of Beam Technology of the Ministry of Education, and School of Physics and Astronomy, Beijing Normal University（教育部束流技术重点实验室，北京师范大学物理与天文学院）；Xinjiang Key Laboratory of Solid State Physics and Devices, School of Physics Science and Technology, Xinjiang University（新疆固态物理与器件重点实验室，新疆大学物理科学与技术学院）
Characterization of a prototype parallel-plate $^{238}$U fission chamber with DD and DT fusion neutron sources
Plasma Science and Fusion Center, Massachusetts Institute of Technology（麻省理工学院等离子体科学与聚变中心）；Commonwealth Fusion Systems（联邦聚变系统）；Coastal Carolina University（海岸卡罗来纳大学）
Effects of 3D printed capsule material on activation thin foil irradiation and counting for fusion neutron yield measurements
Plasma Science and Fusion Center, Massachusetts Institute of Technology（麻省理工学院等离子体科学与聚变中心）；Commonwealth Fusion System（联邦聚变系统）；Coastal Carolina University（沿海卡罗来纳大学）
