HT—7装置工程调试与低温系统长周期供冷

合肥超导托卡马克装置ＨＴ－７已进行了工程调试，在１．４Ｔ环向场下获得脉宽２５０ｍｓ，平顶幅值１６０ｋＡ等离子体电流。其低温系统从１９９５年２月６日至３月６日连续给装置供冷，带有四台活塞式膨胀机的５００Ｗ／４．６Ｋ制冷机通过两次节流或喷射器给装置提供４．５Ｋ两相Ｈｅ流。     

A Ray-Tracing Analysis of ICRH in Tokamaks

Power deposition profiles generated by Ion Cyclotron Resonance Heating （ICRH） in non-circular tokamaks are studied using a ray-tracing technique. The simulation results for the Experimental Advanced Superconductor Tokamak （EAST） D-shaped plasma are presented. It is indicated that the spatial distributions of plasma parameters （plasma density, species temperature, minority ion concentration, etc.） have an significant influence on the power deposition profiles. The findings may be highly useful to the planned plasma heating and experiments in EAST.     

Recent Experimental Progress in the HT—7 Tokamak

Recent experimental campaign in the HT-7 tokamak was scheduled to be ran from November 2002to March 31,2003,During which various issues were in vestgated on geting high electron temperature,long pulse discharges and high performance plasma under quasi-steady-state condition.New systems including LHCD launcher,cryogenic compressor,real-time ploidal control,water-cooled toroidal belt limiter,ferretic liner and several diagnostics were installed and operated to satisfy long-pulse operation requirements.The maximum total injected power was over 1 MW and the longest discharge duration was near to 64 s。     

HT－7托卡马克的八管弹丸注入器

介绍了用于ＨＴ－７托卡马克的的八管弹丸注入器的物理、工程设计原理和结构特点及配置的各种诊断手段。注入器采用气动发射技术，弹丸为１ｍｍ×１ｍｍ，１．２ｍｍ×１．２ｍｍ，１．５ｍｍ×ｌ．５ｍｍ圆柱体氢丸，丸速０．８～１．５ｋｍ／ｓ工作频率１～８Ｈｚ。     

Recent Progress of HT-7U Superconducting Tokamak

HT-7U is a superconducting tokamak. which is being constructed in Institute of Plasma Physics, Chinese Academy of Sciences. The mission of the HT-7U project is to develop a scientific and engineering basis of the steady state operation of advanced tokamak.The engineering design of the device has been optimized. The R&D program is going on. Short samples of the conductor and a CS model coil were tested. All the TF and PF coils will be manufactured and tested in Institute of Plasma Physics. Therefore, a 600-meter long jacketing line for cable-in-conduit conductors along with two winding machines, a set of VPI equipment and a test facility for the TF and PF coils are ready in ASIPP now. In this paper, the recent progress of the HT-7U is described.     

JT—60U稳态运行的约束和稳定性进展

本文介绍了ＪＴ－６０Ｕ托卡马克在建立具有高聚变性能的稳态、完全非感应电流驱动等离子体的物理和技术基础的方面最新成就、最新的结果着重于：（１）高性能反向磁剪切放电「在ＩＰ＝２．８ＭＡ，Ｐａｂｓ＝１７ＭＷ时，理想的等效ＱＤＴ为１．０５，约束增强因子（Ｈ因子）为３．２３，规范化β值为１．８８」，首次观察到电子和离子的热输运势垒；（２）世界上首次注入基于负离子的中性氘束来研究电流驱动、加热和高能粒子行为（     

氘—氚托卡马克等离子体中约束α分布的测量

在ＴＦＴＲ托卡马克氘－氚等离子体芯部，α密度为３×１０＾１６ｍ＾－３时，用光谱测量术观察了能量≤０．７ＭｅＶ的聚变产生的α粒子。在无锯齿放电期间，在ｒ／ａ＝０．３处所测得的能谱与基于碰撞输运所预计的能谱完全一致。在α源关闭之后，α热化期间时间分辨测量表明，分布函数衰减到较低能量是与经典慢化时间０．５ｓ一致的。     

先进托卡马克概念和堆设计

由基于目前在大型托卡马克运行中获得的非常确实的经验的聚变堆设计的讨论中可以得出结论：这些堆在经济上是不具有吸引力的，描述了概念完善的各种选择方案中所涉及到的物理学，给出了某些实验结果的例子，并讨论了对堆经济学的可能影响。