Thermonuclear reactors hold a great promise for the future of Humankind. Within Tokamak and Stellarator reactors, plasma is confined by twisted magnetic fields. Reactors which produce fusion energy have existed since Princeton Large Torus Tokamak in 1978, nevertheless in all reactors built up to now, energy loss from plasma vastly exceeded fusion energy production. In order for a thermonuclear power plant to run, generated fusion energy must significantly exceed energy loss by the plasma. There are four processes by which plasma looses energy -- neutron radiation, Bremsstrahlung radiation, synchrotron radiation, and heat conduction to the walls. For a deuterium -- tritium reactor, 80\% of energy produced by fusion is lost to neutron radiation, about 4\% to 6\% of fusion energy is lost to Bremsstrahlung and synchrotron radiation. For a deuterium -- $^3$He reactor, 5\% of energy produced by fusion is lost to neutron radiation, about 50\% to 75\% of fusion energy is lost to Bremsstrahlung and synchrotron radiation. Increasing reactor operating temperature decreases loss to Bremsstrahlung radiation and increases loss to synchrotron radiation. Power loss to conduction is either independent or weakly dependent on fusion power production. Up to now, no single theoretical or experimental model can accurately predict conduction power loss. For small Tokamaks and Stellarators, conduction power loss vastly exceeds power generated by fusion. For large and powerful thermonuclear reactors which are yet to be built, conduction power loss should be much lower then power produced by fusion.
CuCrZr heat-sink irradiation performance reveals new challenges for thermonuclear fusion reactors
Université Lorraine（洛林大学）；Montanuniversität Leoben（莱奥本矿业大学）；UKAEA (United Kingdom Atomic Energy Authority)（英国原子能管理局）；SCK CEN（比利时核研究中心）；Universidade de São Paulo Escola Politécnica（圣保罗大学理工学院）
Comparison of the Recently proposed Super Marx Generator Approach to Thermonuclear Ignition with the DT Laser Fusion-Fission Hybrid Concept by the Lawrence Livermore National Laboratory
对基于加速器的聚变堆进行了可行性研究。我们考虑了一种新的方案，从加速器的光束击中目标等离子体的聚变反应的共振，并建立一个可行的反应堆的特征标准。在本研究中，我们考虑反应$ d + t \rightarrow n + α, d + {}^3H_e \rightarrow p + α$和$p + {}^{11}B \rightarrow 3 α$。等离子体的临界温度是由聚变能量增益克服束流的阻止本领确定的。所需的等离子体寿命由共振宽度、束流速度和等离子体密度确定。我们估计的临界束流通量的平衡对等离子体的热能和损失，由于停止功率的情况下，惰性等离子体的聚变生产的能量。临界通量与等离子体寿命的乘积与等离子体密度无关，对温度的依赖性较弱。即使这些反应的临界温度低于热核反应堆的临界温度，在惰性等离子体的情况下，临界通量在等离子体密度$ρ_t = 10^{15}/{\rm cm^3}$的$10^{22} - 10^{24}/\rm{cm^2/s}$范围内。讨论了控制双流不稳定性增长的几种方法。我们还考虑了几个实际实施的方案，这些方案需要进一步研究。最后，我们考虑的情况下，注入的光束在共振能量保持等离子体温度和寿命达到稳态。给出了这种情况下的功率平衡方程和粒子数守恒方程。
Dielectronic recombination of lanthanide and low ionization state tungsten ions: W$^{13+}$ - W$^{1+}$
实验热核反应堆ITER目前正在法国卡达拉什建造。反应堆容器将由铍涂层壁和钨涂层偏滤器构成。作为面向等离子体的部件，偏滤器将处于极端温度条件下，导致钨杂质溅射到主体等离子体中。建模和理解这些杂质的潜在冷却效应需要详细的碰撞辐射模型。这些模型需要大量的等离子体中各种原子种类的原子数据。特别是，部分，最终状态解决的双电子/辐射复合（DR/RR）率系数钨是必需的。在这篇手稿中，我们提出了我们的详细的DR/RR率系数的镧系元素，钨的低电离阶段，跨越电荷状态W $^{13+}$ W $^{1+}$的计算。这里提出的计算构成了这种低电离态钨离子的第一个详细的探索。我们能够重现的一般趋势进行计算的其他作者，但发现我们和他们的DR速率系数之间的显着差异，特别是在最低温度下考虑。
Relativistic Six-Fluid Rotating-Plasma Force-Balance Equilibria for p-11B Fusion Conditions in Spherical Tori
Beijing ENN Fusion Energy Science and Technology Co., Ltd.（北京恩诺聚变能源科学与技术有限公司）；Beijing Key Laboratory of High Magnetic Field Spherical Torus Fusion Energy（北京市高磁场球环聚变能重点实验室）；Hebei Key Laboratory of Compact Fusion（河北省紧凑型聚变重点实验室）
