基于变频器的FCS工控网

应用Intellution公司的FIX组态软件,兼容两个8台变频器为从站的工控网CC-link和Profibus-DP。提出了总体方案和配置,实践过程中解决了核心的组网技术。介绍了组态控制过程和应用实例,并对两个工控网作了简单的比较。     

ARIES-AT magnet systems

This report presents a conceptual design of the magnet systems for an advanced tokamak fusion reactor (ARIES-AT). The main focus of the paper is to anticipate and extrapolate the current state-of-the-art in high temperature superconductors and coil design, and apply them to an advanced commercial fusion reactor concept. The current design point is described and supported with a preliminary structural analysis and a discussion of the merits, performance, and economics of high temperature vs. low temperature superconductors in an advanced fusion reactor design.     

汉江安康流域洪水规律分析及水库对安康城区的防洪作用

介绍了汉江安康流域的洪水特点,根据历史洪水资料,多方面分析、归纳了安康洪水的规律;客观论述了安康水电站水库对下游的防洪能力,以及对安康城区防洪减灾发挥的重大作用。     

A simple apparatus for the injection of lithium aerosol into the scrape-off layer of fusion research devices

A simple device has been developed to deposit elemental lithium onto plasma facing components in the National Spherical Torus Experiment. Deposition is accomplished by dropping lithium powder into the plasma column. Once introduced, lithium particles quickly become entrained in scrape-off layer flow as an evaporating aerosol. Particles are delivered through a small central aperture in a computer-controlled resonating piezoelectric disk on which the powder is supported. The device has been used to deposit lithium both during discharges as well as prior to plasma breakdown. Clear improvements to plasma performance have been demonstrated. The use of this apparatus provides flexibility in the amount and timing of lithium deposition and, therefore, may benefit future fusion research devices.     

中国洪水管理战略框架和行动计划

“中国洪水管理战略研究”项目,针对中国洪水管理现状,从中国国情出发,广泛吸收和借鉴国内外洪水管理的成功经验,对洪水管理战略与对策进行了研究,并在深入调研的基础上提出了中国洪水管理战略框架和行动计划设想,以满足全社会日益提高的水安全保障需求,推进由控制洪水向洪水管理的战略性转变,逐步实现以科学发展观和风险管理理论为指导的洪水综合管理。     

The Electron Temperature Estimation Using Soft X-Ray Imaging in HT-7 Tokamak

In order to estimate the electron temperature soft x-ray imaging diagnostics using a double filter technique has been developed in the HT-7 tokamak. The chosen thicknesses of the Be foil are 12.5 μm and 70 μm, respectively. In this article both the main design of the diagnostic configuration and the method to estimate the electron temperature are presented. The results agree with those estimated from the soft x-ray pulse height analyzer （PHA）. The main causes of systematic error have also been investigated.     

Structural materials for fusion reactors

Fusion Reactors will require specially engineered structural materials, which will simultaneously satisfy the harsh conditions such as high thermo mechanical stresses, high heat loads and severe radiation damage without compromising on safety considerations. The fundamental differences between fusion and other nuclear reactors arise due to the 14MeV neutronics of structural materials. There exists considerable uncertainty in the nuclear data at such energies because there aren’t any strong enough sources for such neutrons except fusion reactors themselves! We thus encounter a problem of iterative nature in which we must try several experiments with the available materials in the near term. The development of such structural materials is thus going to require the experimental data of the kind that may be generated on reactors like ITER, high-performance modeling and a penetrating metallurgical insight to overcome technological challenges in terms of achieving required properties such as low activation by controlling the impurities, good thermo-mechanical properties by microstructure engineering, good chemical compatibility and high radiation resistance. These materials need to withstand a neutron wall load of the order of 2–3 MW/m², which can lead up to 30 dpa of radiation damage and 300 appm helium production per full power year in DEMO like reactors. Such conditions lead to unprecedented events related to the failure of materials due to irradiation creep, Ductile-Brittle Transition Temperature (DBTT) shift and helium embrittlement. The development of fusion materials program is oriented towards fulfilling the requirements of Test Blanket Modules, various prototype activities of SST-2 and DEMO reactor. The materials identified for first wall and blanket modules for Indian DEMO are LAFMS and ODS steels. The development program plan for these materials include (i) Manufacturing of LAFMS steel through VIM/VAR methods by controlling the impurities such as S, P and Si. (ii) ODS steel development with nano-size Y₂O₃ dispersoids in ferritic martensitic matrix by powder metallurgy route. The advanced structural materials like SiC_f /SiC composites and SiC_f /n-SiC are planned under National Fusion Program projects for indigenous development. An overview of the planned program in this direction will be presented.     

Study on Modeling Technology in Digital Reactor System

Modeling is the kernel part of a digital reactor system. As an extensible platformfor reactor conceptual design, it is very important to study modeling technology and develop somekind of tools to speed up preparation of all classical computing models. This paper introducesthe background of the project and basic conception of digital reactor. MCAM is taken as anexample for modeling and its related technologies used are given. It is an interface program forMCNP geometry model developed by FDS team (ASIPP & HUT), and designed to run on windowssystem. MCAM aims at utilizing CAD technology to facilitate creation of MCNP geometry model.There have been two ways for MCAM to utilize CAD technology: (1) Making use of user interfacetechnology in aid of generation of MCNP geometry model; (2) Making use of existing 3D CADmodel to accelerate creation of MCNP geometry model. This paper gives an overview of MCAM'smajor function. At last, several examples are given to demonstrate MCAM's various capabilities.     

Characterization of plasma current quench during disruptions at HL-2A

The most essential assumptions of physics for the evaluation of electromagnetic forces on the plasma-facing components due to a disruption-induced eddy current are characteristics of plasma current quenches including the current quench rate or its waveforms.The characteristics of plasma current quenches at HL-2A have been analyzed during spontaneous disruptions.Both linear decay and exponential decay are found in the disruptions with the fastest current quenches.However,there are two stages of current quench in the slow current quench case.The first stage with an exponential decay and the second stage followed by a rapid linear decay.The faster current quench rate corresponds to the faster movement of plasma displacement.The parameter regimes on the current quench time and the current quench rates have been obtained from disruption statistics at HL-2A.There exists no remarkable difference for distributions obtained between the limiter and the divertor configuration.This data from HL-2A provides basic data of the derivation of design criteria for a large-sized machine during the current decay phase of the disruptions.     

先进核能系统设计分析软件与数据库研发进展

参照聚变系统设计研究而获得的实际需求,FDS团队基于现代信息技术发展了一系列先进核能系统设计分析软件与数据库,包括自动建模、物理与工程计算、虚拟仿真与可视化、系统工程与安全分析、数据库及其管理软件等。通过这些软件的发展,促进核科学技术和信息技术学科的深度交叉,探索发展核信息学与技术的途径。本文简要介绍团队开发的各种设计与分析软件的基本发展思路、主要功能与特点、涉及的关键算法与技术以及实际测试与应用情况。