HL-2A托卡马克边界等离子体数值模拟及非日冕平衡条件下的杂质辐射问题研究

对边界层等离子体中常见的物理问题，从两点模型到二维流体描述。从原子分子物理过程到杂质的输运和辐射等进行了系统的归纳和总结，特别是对等离子体不同参数运行区如鞘层限制参数区、传导限制参数区以及脱靶参数区等的一维流体描述，在参阅相关文献的基础上使用一定的假设条件进行了简单推导。分别阐述了它们的特点。     

Tritium Burn-up Depth and Tritium Break-Even Time

Similarly to but quite different from the xenon poisoning effects resulting from fission-produced iodine during the restart-up process of a fission reactor, we introduce a completely new concept of the tritium burn-up depth and tritium break-even time in the fusion energy research area. To show what the least required amount of tritium storage is used to start up a fusion reactor and how long a time the fusion reactor needs to be operated for achieving the tritium break-even during the initial start-up phase due to the finite tritium breeding time that is dependent on the tritium breeder, specific structure of breeding zone, layout of coolant flow pipe, tritium recovery scheme, extraction process, the tritium retention of reactor components, unrecoverable tritium fraction in breeder, leakage to the inertial gas container, and the natural decay etc., we describe this new phenomenon and answer this problem by setting up and by solving a set of equations, which express a dynamic subsystem model of the tritium inventory evolution in a fusion experimental breeder （FEB）. It is found that the tritium burn-up depth is 317g and the tritium break-even time is approximately 240 full power days for FEB designed detail configuration and it is also found that after one-year operation, the tritium storage reaches 1.18kg that is more than the least required amount of tritium storage to start up three of FEB-like fusion reactors.     

杂质靶丸注入在ITER诊断中应用的可行性

国际热核实验堆ITER-FEAT设计已完成。在ITER中,α粒子诊断是运行控制方面的一个关键性问题。从Kuteev的氢类靶丸消融理论出发,导出了杂质靶丸的半径烧蚀速率和粒子消融速率。并对杂质靶丸注入在未来ITER中作为α粒子诊断的可行性进行了探讨。计算和理论分析表明锂靶丸具有较多兼容性,既可用作α粒子诊断也可测量等离子体的q分布。     

改善ITER 弹丸注入芯部加料的研究

研究了五种不同组合的固态氢同位素靶丸H₂、HD、D₂、DT 和T₂ 在聚变等离子体中的消融率。结果表明, 燃料靶丸的同位素效应, 可导致更深的靶丸消融物质沉积。在同样的本底等离子体条件和弹丸初始参数下, 注入氚丸比氢丸的穿透深度增加约40%。适度减轻一些ITER 的加料困难。进一步的研究表明从中平面高场侧注入靶丸对芯部加料有显著改善。考虑托卡马克非均匀磁场的影响, 被电离的消融云内的垂直漂移电流产生极化, 引起带电消融物沿大半径方向朝外漂移。数值模拟计算表明, 只要用初始速度为每秒几百米的低速弹丸, 便能使靶丸的消融物质沉积到ITER 等离子体中心。     

HL-1装置的磁场测量

本文叙述了HL-1装置环向场线圈、内外垂直场线圈,欧姆变压器初级绕组和偏磁绕组的磁场测量方法和结果,初步讨论了带有切口的铜壳对磁场的影响。     

高热负荷下偏滤器材料的温度测量

用小试样模拟试验测试了不同功率密度下的材料表面温度分布。用热等静压焊接方法制作了钨为表面的模拟偏滤器材料小试样,用 25mm的电子束作为热源,在真空室中用 0.3mm的NiCr NiSi热电偶测量了2～9MW·m-2功率密度下材料表面的温度分布。结果发现在充分冷却的情况下,表面最高温度约400℃,钨铜焊缝处的平均温度达150℃。     

HL-2A偏压偏滤器物理设计

根据已有的理论模型,推算出了HL-2A偏压偏滤器的理论电流为1．5kA、偏压电压为200V,并对HL-2A偏压偏滤器做出了初步设计。HL-2A装置采用偏压后,有可能降低L-H模转变阈功率,增加偏滤器等离子体密度、压强和滞留时间,改善约束,改善内外靶板功率沉积的非对称性,提高排灰效率及提高偏滤器性能。     

Quantum Effects on the Coulomb Logarithm for Energetic Ions During the Initial Thermalization Phase

We have discussed the quantum mechanical effects for the energetic charged particales produced in D-He^3 fusion reactions.Our results show that it is better to use the proper Coulomb logarithm at the high-energy end in describing the thermalization process,because the quantum mechanical effects on the Coulomb logarithm are not negligible,based on an assumption of binary collision.     

大脉冲热负荷下HL-2A偏滤器靶板的热分析

HL－2A安装完成后,将以ASDEX最终的运行参数水平进行工程调试。本文研究了,在仅有欧姆加热和3.5MW中性束注入条件下,当HL－2A发生大不稳定性或巨ELMs爆发时,有水冷却和辐射冷却两种情况下不同板材料偏滤器板的温升和冷却时间。