堆芯燃料组件流阻特性模块式与整体式三维数值模拟方案比较

组件的阻力特性影响堆芯不同类型组件的流量分配,对堆芯的设计起到至关重要的影响。为提高验证堆芯燃料组件特性的求解精度及效率,本文针对燃料区6类燃料组件中的两类进行模块式及整体式三维数值模拟,获得了两类组件的流阻特性,并用相同条件下的全组件试验结果进行了对比。结果表明：推广至堆芯所有燃料组件流阻特性预测,模块式所需计算时间约为整体式的1/6,但整体式三维数值模拟所得压降与试验结果吻合度高,误差较模块式小。最后深入研究了流速及温度变化对流阻特性的影响。该研究为后续各类组件的流阻特性研究方法选取提供技术支持。     

Plasma Shape and Current Control Simulation of HT-7U Tokamak

This paper describoes the discharge simulation of HT-7U tokamak plasma equilibrium and plasma current by solving MHD equations and surface average transport equations using an equilibrium evolution code. The simulated result shows the evolution of plasma parameter versus time .The simulated result can play an important role in the design of the plasma equilibrium and control system of a tokamak.     

Structural design of cryogenic component support for EAST （HT-7U）

EAST is a full superconducting tokamak with an elongated plasma cross-section. It consists of superconducting poloidal field (PF) magnet system, toroidal field (TF) magnet system, vacuum vessel with inner parts, thermal shields and cryostat vessel. The mission of the project is to widely investigate both physics and technologies of advanced tokamak operations, especially the mechanism of power and particle handling for steady-state operations. The cryogenic component is mainly composed of superconducting TF and superconducting PF coils that ensure the ability of sustaining magnetic field for plasma confinement, control and shaping in steady-state. This report describes the process of the structure design of cryogenic component support for EAST.     

HT-7U超导托卡马克装置真空室热烘烤结构数值模拟与分析

在等离子体运行前．为了提高真空室的本体真空度,获得一个高真空等离子体运行环境,必须对真空室进行250℃壁处理烘烤．除去吸附在器壁表面上的杂质。基于此,本文提出了电阻丝和气流加热两种烘烤方案,并对其结构进行了数值模拟和分析．得出了真空室烘烤时的加热功率、温度分布和热应力情况,为HT-7U和同类超导托卡马克装置真空室烘烤结构的工程设计和优化提供了理论参数依据。     

The Positions and Number of Flux Loops and Magnetic Probes for the HT—7U Superconducting Tokamak

The plasma shape and other paremeters such as βp,li is important for the tokamak deveice where the palsma has a non-circular cross-section of sufficient elongation.The measuered signals of magnetic probes and flux loops are used to reconstruct the plasma shape and the current profile in device operation and plasma shape feed back control system.So the number and positions of magnetic probes and flux loops provides the basis of the plasma reconstruction.This paper instroduce how to use EFIT code (equilibrium fitting code)to determine the number and positions of the magnetic probes and flux loops.The simulation result is given also.     

中国先进研究堆标准燃料组件三维流场分析

采用计算流体力学软件CFX4.4和CFX5.5对中国先进研究堆标准燃料组件流场进行了数值模拟。计算得到了额定工况下标准燃料组件内各个冷却剂通道的流量分布和不等间隙通道燃料板两侧压差。根据不同流量下的压降计算结果,给出了标准燃料组件的阻力特性曲线,并与试验结果进行了比较,符合较好。     

Design and Simulation for the Pulse High-Voltage DC Power Supply (HVPS) of 1.2 MW/2.45 GHz HT-7U Lower Hybrid Current Drive System

1. IntroductionThe HVPS [2] (pulse high-voltage DC power supply) in design will not only supply power to theklystron of the future HT--7U, but also is ajccommodated to the LHCD system on the existing HT--7.Though the old power supply fed by both 10 kV electric grid and 120 MW/10 s AC--pulse gener'ator hasbeen applied reliably on the low hybrid current drivesystem of 1.2 MW/2.45 GHz HT--7, but causes muchtroubles to LC filter due to indeterminate phase difference in electric grid and…     

中国实验快堆工程主工艺管系及设备三维校核设计

利用三维软件模拟设备及管系，在计算机上实现设备和管系的预安装，提前发现并解决中国实验快堆工程系统布置和安装过程中存在的问题。文章论述了三维校核设计的应用背景、技术方案、具体实现，给出了效果图例。     

Benchmarks of 3D Laplace Equation Solvers in a Cubic Configuration for Streamer Simulation

The aim of this paper is to test a developed SOR R&B method using the Chebyshev accelerator algorithm to solve the Laplace equation in a cubic 3D configuration.Comparisons are made in terms of precision and computing time with other elliptic equation solvers proposed in the open source LIS library.The first results,obtained by using a single core on a HPC,show that the developed SOR R&B method is efficient when the spectral radius needed for the Chebyshev acceleration is carefully pre-estimated.Preliminary results obtained with a parallelized code using the MPI library are also discussed when the calculation is distributed over one hundred cores.     

Simulation of the Background for Gamma Detection System in the Indoor Environments of Concrete Buildings

The indoor background has significance in determining the minimum detectable level of gamma detection systems. The gamma radiation field in a concrete building was studied by using the Monte Carlo simulations. The parameters of wall thickness, room shape and dimensions were considered in the modeling. A spherical layer model was assumed as the indoor source geometry with the intention of easy and effective calculations. The simulation model was applied to an unshielded germanium detector and the detection system with a more complex shielding configuration. As the results, the indoor radiation field in the concrete building can be predicted well by assuming the source geometry of a spherical concrete layer with a real thickness and the homogeneously distributed source of the natural major three components, the ²³⁸U series, ²³²Th series and ⁴⁰K. The simulation model is useful for designing and optimizing gamma detection systems or shielding assemblies.     

Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal–hydraulic 3D kinetics code

The modeling of complex transients in nuclear power plants (NPP) remains a challenging topic for best estimate three-dimensional coupled code computational tools. This technique is, nowadays, extensively used since it allows decreasing conservatism in the calculation models and performs more realistic simulation and more precise consideration of multidimensional effects under complex transients in NPPs. Therefore, large international activities are in progress aiming to assess the capabilities of coupled codes and the new frontiers for the nuclear technology that could be opened by this technique. In the current paper, a contribution to the assessment and validation of coupled code technique through the Kozloduy VVER100 pump trip test is performed. For this purpose, the coupled RELAP5/3.3-PARCS/2.6 code is used. The code results were assessed against experimental data. Deviations between code predictions and measurements are mainly due to the used models for evaluating and modeling of the Doppler feedback effect. Further investigations through the use of two “antagonist” uncertainty GRS and the CIAU methods, were considered in order to evaluate and quantify the origin of the observed discrepancies. It was revealed on one hand that relative error quantification discrepancies exist between the two approaches, and further enhancements for both methods are needed.