核聚变实验装置HT-7U及大厅活化分析

使用一维ＳＮ离散坐标法输运程序ＡＮＩＳＮ、活化计算程序ＡＦＤＫＲ并使用一维球几何模型对ＨＴ－７Ｕ装置米要部件及混凝土屏蔽墙的活化进行了计算和分析,给出了中子能谱、γ能谱、大厅内外剂量率空间分布及放射性水平的时间分布,对ＨＴ－７Ｕ装置的主要中子学参数及周围居民接收剂量水平给出了定量的分析。     

二维中子-光子输运计算程序DOT3.5在核聚变实验装置HT-7U辐射屏蔽设计中的应用

利用二维中子－光子输运程序ＤＯＴ３．５计算和分析ＨＴ－７Ｕ在Ｄ－Ｄ放电运物时实验大厅内外的中子、光子通量及剂量当量率的空间分布,并评估大厅顶部不同防护材料的屏蔽效果,为辐射防护设计提供参考。     

核聚变装置HT-7U环境辐射剂量蒙特卡罗模拟计算与分析

在聚变评价数据库FENDL／2的基础上，采用三维蒙特卡罗输运程序MCNP／4C，对核聚变装置HT07U运行时的环境辐射剂量率进行了模拟计算及相关分析，着重研究了HT-7U硼水屏蔽层不同设计方案对环境剂量率的影响。计算结果表明，硼水层有效地减小了装置运行时周围环境的辐射剂量率，而浓缩硼水方案相对天然硼水方案，屏蔽效果提高不明显。同时本文也对聚变装置环境辐射剂量计算中的天空反(散)射效应进行了初步的研究，计算结果显示，当屏蔽大厅顶厚减至0．5m以下时，装置运行时大厅外辐射剂量分布呈现明显的阴影效应。     

核聚变实验装置HT-7U停机辐射剂量率三维计算与分析

在基于三维蒙特卡罗方法的聚变装置停机剂量率计算方法“严格两步法”(R2S)的基础上,首先建立了核聚变托卡马克实验装置HT-7U三维精确模型,然后对HT-7U各种D-D放电模式下的停机剂量率进行了详细的三维计算与分析,从而为装置实验方案及实验维修人员的安全操作规程的制定提供了理论基础,也对装置的辐射防护问题具有参考价值。     

Remote Control for the HT-7 Distributed Data Acquisition System

HT-7 is the first superconducting tokamak device for fusion research in China. Many experiments have been done in the machine since 1994, and lots of satisfactory results have been achieved in the fusion research field on HT-7 tokamak^[1]. With the development of fusion research, remote control of experiment becomes more and more important to improve experimental efficiency and expand research results. This paper will describe a RCS (Remote Control System),the combined model of Browser/Server and Client/Server, based on Internet of HT-7 distributed data acquisition system (HT7DAS). By means of RCS, authorized users all over the world can control and configure HT7DAS remotely. The RCS is designed to improve the flexibility, opening, reliability and efficiency of HT7DAS. In the paper, the whole process of design along with implementation of the system and some key items are discussed in detail. The System has been successfully operated during HT-7 experiment in 2002 campaign period.     

一维中子-光子输运程序ANISN在核聚变实验装置HT-7U周围环境辐射剂量计算中的应用

在一维几何模型的基础上采用ＮＡＩＳＮ程序,计算并分析了ＨＴ－７Ｕ超导Ｔｏｋａｍａｋ在Ｄ－Ｄ放电时周围环境辐射剂量当量率的变化规律,计算与分析的结果可供Ｔｏｄａｍａｋ核聚变实验装置作环境评价和防护设计参考。     

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.     

Modification of Boundary Parameters and Fluctuations by IBW and LHCD in the HT-7 Tokamak

Measurements of boundary parameters and their fluctuations have been performed in ohmic (OH) plasma and Ion Bernstein Wave (IBW) and Lower Hybrid Current Drive (LHCD) enhanced confinement plasma using a pneumatically driven Langmuir probe array on HT-7 toka-maX. In the enhanced confinement plasma~ the gradients of electron density and temperature become higher and a transport barrier comes into being in the vicinity of the limiter. The boundary potential shows a clear modification in the same region. The fluctuation levels are significantly depressed and the coherences between fluctuations are reduced evidently in the enhanced plasma.Meanwhile, we obtained the spectral features and the poloidal phase velocity of fluctuations us-ing a two-point correlation technique and found obvious modifications of the turbulence and the poloidal flow. The results suggest that the improved confinement in the IBW and LHCD enhanced plasma is at least partially due to the modification of the boundary parameters and the suppression of the boundary fluctuations and fluctuation induced fluxes.     

托卡马克HT-7U低温超导磁体的绝缘系统

主要介绍低温超导托卡马克HT-7U中磁体的绝缘结构,绝缘材料的特性,绝缘结构形成的工艺,绝缘层的电性能和力学性能等。     

Data Processing and Acquisition System for the HT-7 Multipulse Thomson Scattering Diagnostic

This article describes the data processing and acquisition system for the HT-7 multipulse Thomson scattering diagnostic. An eight-pulse laser is used in the Thomson scattering system to obtain electron temperature profiles at eight different times throughout an entire plasma discharge. The major components of the diagnostic system consist of a multipulse iNd-glass laser,a photodetector‘‘s subsystem, a calibration set and a CAMAC data processing and acquisition system. The data processing software along with LeCroy 2250L will perform the data acquisition.In order to simplify the operation and extend the capability of its compatibility with other math softwares, the processing software has been improved by the authors. The new software based on the VC easily utilizes some math softwares to calculate the electron temperature. The new software is simpler and more operational than the old one.     

Superconducting Busline Design for HT—7U Tokamak

Superconducting (SC) tokamak HT-7U has seven pairs of buslines connecting toroidal/Poloidal coils and the current leads,These SC buslines(SCBLs) share a common cryostat and are made of the calbe in conduit conductors(CICCs) arranged as a decoupling configuration.In order to reduce the heat loads conducted from the seven current leads with a capacity of 15kA during the magnets cooldown.the buslines with a much lower thermal conduction were employed in comparison with the current leads,and a special cooling loop was designed.     

Preliminary Design of Control Network for HT-7U Tokamak Cryogenic System

In the course of the cryoplant modernization,a control network will be set up inorder to facilitate the control,the supervision,the centralized data acquisition and the alarmhandling of the cryogenic system for HT-7U tokamak.The paper introduces the preliminarydesign of control network based on the Controller Link Network for HT-7U tokamak cryogenic     

Insulating process for HT-7U central solenoid model coils

The HT-7U superconducting Tokamak is a whole superconducting magnetically confined fusion device. The insulating system of its central solenoid coils is critical to its properties. In this paper the forming of the insulating system and the vacuum-pressure-impregnating (VPI) are introduced, and the whole insulating process is verified under the superconducting experiment condition.     

Design of flowing liquid lithium device for HT-7 tokamak

Lithium is a very attractive element due to its very low radiation power, strong H retention as well as strong O getter activity. Flowing liquid lithium (FLiLi) device, to be used as a plasma-facing limiters, has been designed and will be tested in HT-7 tokamak. It is mainly composed of distributor, guide plate, collector, and heater as well as cooling loop. The heater uses heater strip and cooling loop design, to control the temperature of lithium on the guide plate ranging from 200 °C to 400 °C. The distributor attached to feeding pipe, distributes liquid lithium (LiLi) flowing on the guide plate. The collector was designed to reclaim the superfluous LiLi and transport it out of device.The paper focuses on the design of flowing liquid lithium device. In addition to the process of design, thermal analysis has been carried out using finite element method (FEM) for optimizing the structure of heater and cooling loop and results of analysis are presented.     

HT-7积分器系统的定时触发模块设计与实现

本文设计一种积分器系统中的定时触发模块,详细介绍用单片机和晶体管设计定时触发模块的设计思路、硬件结构和软件设计等方面的内容.该模块为积分器系统提供精确的可词积分定时时间,且触发准确、驱动能力强.定时触发模块提高了积分器系统的可靠性和适用范围,满足HT-7实验要求.     

A Calculation of Steady Pressure Drop and an Analysis of HT—7U CICC

Under the condition of steady,the pressure drop of coolant is mainly caused by friction along the cable.in the CICC(cable-in-conduit-conductor).helium flow within the conductor consists of two parallel interconnected tubes.The velocity distribution has some differece between the central channel and conductor space.The region of Reynolds number is from 10^3 to 10^6.This paper describes the calculation of pressure drop of HT-7U CICC at various mass flows.It is assumed that the coolant flows in two parallel,rough tudes during the caclulation.