“氚坑深度”和“氚坑时间”

裂变堆中的氙-135中毒效应是由于裂变产生的碘-135经由β衰变产生氙。135，后者吸收中子的截面很大，如停堆时剩余反应性不够，就要经过一段“碘坑时间”才能恢复到原来停堆前的反应性后才正常工作起来。与此类似却有所不同的一个全新的概念，“氚坑深度”和“氚坑时间”首次被我们引入到聚变堆研究领域，它表明为了实现“得失相当”，起动一个聚变堆所要求的最少氚储备和运行时间。“氚坑深度”和“氚坑时间”与具体的氚回收方案、提取氚的工艺过程、堆部件材料中的氚扣留量、增殖剂中不可回收的氚份额、泄漏到堆大厅的包容惰性气体氦中的份额以及氚自然衰变等等有关。     

FEB氦灰问题研究

本文从现有的氦灰输运和排除的实验数据出发，计算了ＦＥＢ的氦灰积累速率，得到了平衡氦灰浓度，另外，从α粒子平衡方程和等离子体功率平衡方程出发得到的结果与直接从实验数据计算得到的结果相一致。最后，用二维Ｍｏｎｔｅ－Ｃａｒｌｏ程序模拟了排灰效率与偏滤器工程结构参数和靶板附近的等离子体参数之间的敏感性关系。     

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.     

SWITRIM��������ƺ�ʹ�øſ�

研制出了用于计算氚投料量在FEB聚变堆各个子系统中的分布及其随时间变化的数值模拟程序包SWITRIM。通过近5年的使用，表明其运行良好、计算结果可靠。用SWITRIM数值模拟研究了聚变堆起动过程中的“氚坑深度和氚坑时间”新现象。简单介绍了SWITRIM程序包的组成和用户使用说明以及最新的运用等。     

聚变等离子体中的快离子压强

本文运用Fokker-Planck方程的慢化近似,考虑存在多种离子成份(包括杂质),假定它们具有共同的温度,我们得到了聚变产生的快离子压强的简单封闭形式表示式。表明在典型的工作温度下(～60keV),D-~3He等离子体中聚变产生的快离子压强约为本底热压强的20％,这与D-T等离子体工作在20keV时的比值几乎相同。因此,D-~3He和D-T在它们相应的预期工作温度下,它们各自的快离子压强对总压强的影响是类似的,然而在更高的温度下,这个比值将变得更大。     

D—^3He聚变动力可行性研究

本文首先简要地讨论D-3He聚变的物理要求并与D-T聚变作相应的比较,然后运用目前的约束定律和第一稳定区β极限,对计划的近期ETR规模装置(如CIT,TIBER,FER,NET)进行D-3He得失相当和点火实验的可行性研究,并对高径比第二稳定区D-3He托卡马克堆进行参数学研究,最后指出潜在的缩短商用化进程可能性。     

FEB-E 氚泄漏分析

用Ｓｉｅｖｅｒｔｓ定律和ＳＷＩＴＲＩＭ编码研究了聚变实验增殖堆的工程概要设计ＦＥＢ－Ｅ在正常工作状态和事故状态下的氚泄漏问题,分析表明,在这两种状态下ＦＥＢ－Ｅ包层液态锂中氚的分压都不高,氚泄漏的主要危险来自偏滤器的抽气系统的气体漏失。     

Effects of a liquid lithium curtain as the first wall in a fusion reactor plasma

This paper explores the effect of a liquid lithium curtain on fusion reactor plasma, such curtain is utilized as the first wall for the engineering outline design of the Fusion Experimental Breeder （FEB-E）. The relationships between the surface temperature of a liquid lithium curtain and the effective plasma charge, fuel dilution and fusion power production have been derived. Results indicate that under normal operation, the evaporation of liquid lithium does not seriously affect the effective plasma charge, but effects on fuel dilution and fusion power are more sensitive. As an example, it has investigated the relationships between the liquid lithium curtain flow velocity and the rise of surface temperature based on operation scenario II of the FEB-E design with reversed shear configuration and high power density. Results show that even if the liquid lithium curtain flow velocity is as low as 0.5 m/s, the effects of evaporation from the liquid lithium curtain on plasma are negligible. In the present design, the sputtering of liquid lithium curtain and the particle removal effects of the divertor are not yet considered in detail. Further studies are in progress, and in this work implication of lithium erosion and divertor physics on fusion reactor operation are discussed.[第一段]     

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。