Table of Content

15 June 2005, Volume 25 Issue 2

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Contents

Characteristics of the single null divertor of the HL-2A tokamak

SHI Bing-ren, SHI Ying-tian, YUAN Bao-shan

2005, 25(2):  81-83. 

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Characteristics of the single-null divertor configuration of theHL-2Atokamak are studied by using the in- tegral approach for various current profiles. The advantage of this approach is its suitability for solving the free boundary Grad-Shafranov equationwith X-points for arbitrary current profile. For theHL-2Atokamak, the required disposal of the currents in different poloidal coils (the vertical field coils, the three mult-i polar coils, the compensated mult-i polar coils and the horizontal coils) can be appropriately determined through a few iterations under a reasonable initial assumption about the plasma boundary. The boundary of the single-null diverted plasma in the HL-2A tokamak is simply a circular one plus a local triangular deformation near the X-point. The merit of this divertor configuration is studied by following several magnetic field lines in the scrape-off layer.

Studies of the target fuel depletion and energy gain of inertial confinement fusion with D-3He advanced fuel

DENG Bai-quan, FENG Kai-ming

2005, 25(2):  87-92. 

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The target fuel depletion and energygain of inertial confinement fusion (ICF) for uniformspherical target of D-³He advanced fuel compressed by high power mult-i laser-beam have been calculated in this article. In order to ex- tract the fusion energyfromthe fusion reaction chamber, a newkind of porouswetwall of free surface liquid lithium,con- sisting of an array of capillaries, with ant-i radiation and automatic renewal properties, has been designed. The energy balance of this reactor system is discussed, and the difference of the fuel depletion fraction, energy gain and other eng-i neering characteristics are compared with similar D-Tfuel target reactor system.

Analysis and design of neutronics for an ITER test blanket module

ZHANG Guo-shu, FENG Ka-i ming, YUANTao, CHEN Zhi

2005, 25(2):  93-98. 

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Neutronics designs and calculations lay the foundation for the systems of ITER test blanket module(TBM). In this paper, firstly, a newmult-i group nuclear data library based on the FENDL2.0 data library is processed with the TRANSX code and a benchmark calculation is performed in order to check the correctness of code and data library. Then, by means of the 2-dimensional TWODANT code, the distribution of power density, tritiumgeneration, neutron irradiation, hydrogen generation and helium generation in the China Helium Coolant Solid Breeder Test BlanketModular (CHHC-SBTBM) are calculated. Finally, preliminary neutronics designs of CHHC-SBTBMare givenwith a reasonable optimization.

Design of ITER vacuum vessel neutron shielding structure

LIU Chang-le, WU Song-tao, YU Jie, CAI Ying-xiang

2005, 25(2):  99-104. 

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Neutron shielding structure of the ITER vacuum vessel (VV) will be applied to shielding neutron and gamma-ray and reducing the toroidal field ripple. The features of ITER vacuum vessel and the material selection for shielding structures are briefly discussed. Ashielding conceptual design and some correlative supportstructures have been developed. The layoutof ferromagnetic insertswas performed. Fillingratios of shieldingmaterials betweenVVshellswere acquired according to ITER VV physics calculation results. In term of the ITER VV design criteria, the detailed design work for library of the shielding blocks and the emulational structure have been finished based on the 3D modeling soft- ware.

Development of a prototype neutron flux monitor for ITER

YANG Jin-wei1, ZHANGWei1, SONG Xian-ying1, LI Xu1,LI Wen-zhong1, WANG Sh-i qing1, XIAO Gong-shan2, LUShuang-tong2

2005, 25(2):  105-109. 

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A new fission chamber assembly has been developed,aiming to support the design of this ITER compo- nents. The fission chamber assembly includes two ²³⁵U fission chamber detectors and a/blank0detector of same dimen- sions butwithout fissile materials, to identify noises fromgamma-rays, X rays, etc. The assemblymain parameters mea- sured in the laboratory approach the recent level of ITER. After further development and modification, itwill be used as the neutron flux monitor for the phase of D-D fusion of ITER.

Two problems in the numerical simulation of laser-plasma eradiating X-rays

HUANG Wei, CHANG Wen-wei, MAYan-yun, LI Di

2005, 25(2):  110-114. 

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A Runge-Kutta algorithm is used in solving the ray equations for the numerical simulation of laser-plasma eradiating X-rays.We discuss the evident algorithm.s feasibility of the rate equations of electron.s occupation probabi-l ities needed in getting the X-ray.s eradiation. The calculated results showthat these methods are effective and feasible.

Simulation investigation of the effect of IBW on LHCD

(中国科学院等离子体物理研究所,合肥230031)

2005, 25(2):  115-118. 

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The power deposition profile of the lower hybrid wave (LHW) and the distribution of the current driven byLHWunder the local synergistic interaction ofLHWand ion Bernsteinwave (IBW) have been studied using advanced ray-tracing and 2-DFokker-Planck numerical code. The numerical simulation results showthatthe LHWpower deposition profile and the driven current distribution are modified due to the interaction of IBWwithLHW, IBWabsorption by elec- trons via electron Laudau damping (ELD) around the maximums ofn+offering a possible mechanismof plasma heating, and the efficiency of LHCD is improved.

Cause of ceramic window breakdown and its improvement for the HT-7 LHCD system

HUANG Feng1,2, SHAN Jia-fang1, KUANG Guang-li1

2005, 25(2):  119-123. 

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The cause of the breakdown of ceramicwindowin theHT-7 LHCD systemhas been analyzed accordingto the experiment data and experiment phenomenon. Suggestions for the improvement of the equipment have been made.

Manufacture of the rectifier of the HT-7U PFPS

GAO Ge, FUPeng, TANGLun-jun, WANGLin-sen

2005, 25(2):  124-128. 

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The rectifiers of the HT-7U poloidal field power supply (PFPS) are introduced. A new control method, four quadrants converter, is brought forward, which overcomes the shor-t coming of both the circulating current mode and the non-circulating current mode. This control mode also resolves the problem of DC circulating current in the identical phase ant-i parallel connection rectifiers when these rectifiers run in the circulating current mode.

A study on capacity-coupled segmented discharge plasma

MA Teng-cai, ZHANG Yu-tao, REN Chun-sheng,QI Bing, WANG Da-wang, WANG Kun

2005, 25(2):  129-132. 

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Capacitor-coupled segmented discharge, a newmethod of plasma generation in atmospheric air, is proposed. It concentrates the merits of corona discharge and dielectric barrier discharge (DBD), which can produce a large- scaled, tense,and homogeneous non-thermal plasma. Its discharge power is more than 100 times of the traditional DBD, and it can be modulated flexibly.

Structural design and analysis of forces for the thermal shield of the EAST tokamak

XIE Han, LIAO Zi-ying

2005, 25(2):  133-138. 

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The EAST is a tokamakwith superconducting toroidal and poloidal magnets operating at 4K. In order to reduce the thermal load applied to surfaces of all cryogenically cooled components and keep the heat load of the cryogenic systemminimal, a continuous radiation shield system located between the magnet system and the warm components is adopted. The EAST thermal shield system consists of vacuum vessel thermal shield and cryostat thermal shield. The NASTRAN finite element softwarewas employed to calculate different load conditions of the thermal shield after analyzing the thermal stress in operation and electromagnetic forces under plasma disruptions for optimization design of the structure.

New bipartition model of neutral particle transport in the HL-2A divertor region

DENG Bai-quan, YAN Jian-cheng, PENG Li-lin

2005, 25(2):  139-145. 

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A new bipartition neutral transport model has been developed for simulation of the hydrogenic neutral particle transport in the vicinity of HL-2A divertor target plate.The numerical calculation results on the basis of this model are fairly consistentwith the results obtained with the "multi-generation method". One possible application of this model is to provide a source term originating from neutral transport calculation for any other edge plasma transport code, for instance, B-2 code, which has been used to simulate edge plasma transport of the HL-2A divertor configuration. Especially it can be utilized to quickly classify the plasma in divertor region as high or low recycling regime.

Analysis for dynamic stability of the cantilever conductive thin plate under transverse triangular impulsive magnetic field

ZHANG Jian-ping

2005, 25(2):  146-152. 

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For the cantilever conductive thin plate under only externally lateral triangular impulsive magnetic field, the quantitative analytical method of dynamic stability is given to the plate which is subject to the effect of the impulsive magnetic field. In virtue of the magnetic body force produced by the interaction between eddy current and total magnetic field, the buckling problem is displayed. When the different stationary magnetic fields are set, a numerical program is established to simulate the magnetoelastic dynamic responses of the conductive thin plate subjected to a triangular impulsive magnetic field. After that, we give the regions of the dynamic stability on the parameters of the values of stationary magnetic field, the apexes of transverse impulse magnetic field, and the impulse duration.

Divertor physics analyses and preliminary experimental results on the HL-2A tokamak

WANG Xiang-xing, YANLong-wen, HONGWen-yu, QIAN Jun

2005, 25(2):  153-156. 

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Edge plasma parameters of both linearregime and high recyclingregime in the HL-2A tokamak are calculated using the/two-point0model of divertor physics analyses. They include the plasma temperature, density and incident power on divertor target, and decay lengths of upstreamplasma temperature, density and incident power. The target temperature and density predicted with the model of linear regime are in good agreementwith experimental results.

Measuring the HL-2A edge plasma with a fas-t speed single probe

HONG Wen-yu, PAN Yu-dong, WANG En-yao, YAN Long-wen, QIAN Jun

2005, 25(2):  157-160. 

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Measurments of the HL-2A edge plasma near the mid-plane with a fast speed single probe are presented in the paper. The Langmuir probe is mounted on a long shaft, which can be shifted radially and rotated circularly. The radial profiles of the plasma edge electron temperature, density, floating potential, spacing potential and poloidal flowve- locities have been measured utilizing a 1MHz fast sampling module. The results obtained showthat radial profiles of the temperature and the density measured with the single probe are in agreement to those with a four-probe system.