Optimized mass flow rate distribution analysis for cooling the ITER Blanket System

This paper presents the rationale to the optimization of water distribution in ITER blanket modules, meeting both Blanket System requirements and interface compliance requirements.The key challenging constraints include to: be compatible with the overall water allocation (3140 kg/s for 440 wall mounted BMs); meet the critical heat flux margin of 1.4 in the plasma facing units; meet a maximum temperature increase of 70 °C at the outlet of each single BM; and ensure that water velocity is less than 7 m/s in all manifolds, and that the pressure drops of all BMs can be equilibrated. The methodology and the successful result are presented.     

汽轮机跳闸反应堆不停堆试验瞬态分析与设计优化

田湾核电站一期工程2台机组在调试期间共进行了8次汽轮机跳闸反应堆不停堆试验,由于首次采用混合式2号低压加热器及全数字化仪控系统,试验阶段发现了一些问题并进行了设计优化。本文重点介绍了田湾核电站1号机组100%FP功率平台的汽轮机跳闸反应堆不停堆试验情况,包括试验目的,验收准则和试验的实施;详细分析了试验过程中瞬态现象及调节系统的响应情况;综合分析了1、2号机组历次停机试验发现的问题及设计优化方案。     

汽轮发电机厂房底板的设计改进

介绍了汽轮机厂房地板超厚问题 ,以及业主是如何通过理论研究实践经验据理迫使Bechtel公司接受并按照业主的意见修改了设计 ,从而节省了大量的投资的情况。同时 ,反映了业主对设计进行审查的必要性和重要性     

上海EBIT动态控制电路设计

通过对上海EBIT装置离子注入引出系统的分析,采用FPGA为控制逻辑单元来设计EBIT装置的动态控制电路,实现了对EBIT装置中离子“注入-引出-电离”的动态控制。上海EBIT动态控制系统包括了基于FPGA的控制电路的设计和用户控制界面的设计。采用FPGA来设计EBIT动态控制系统,提高系统的控制速度和精度。     

Power control of CANDLE reactor by coolant flow rate

CANDLE reactors do not require control rods for burn-up control. Such reactors can achieve the excellent features of previously-considered CANDLE reactors such as constant power shape and reactivity feedback coefficients during the entire operation period at the rated power level. By eliminating control rod use for power level control, the CANDLE reactor can be operated in a load-following mode and its utility will expand dramatically.By numerical calculations, power control by coolant flow rate was studied for the sodium-cooled metallic fuel large CANDLE reactor. The effect of thermal expansion of the core support structure shows considerable contribution toward achieving negative reactivity feedback to improve the power controllability. We employ HT-9 and SUS316 for core support structures. Since the maximum cladding temperature reaches its design constraint, power level cannot be decreased less than its lower limit, which is 66% for HT-9 and 57% for SUS316.     

大型集装箱CT检测系统PID控制设计

简要介绍了大型集装箱CT检测系统的原理及其控制系统结构,分析了PID控制系统的组成,并详细介绍了PID控制算法和参数整定方法.系统的实际运行结果表明,选择合适参数的PID控制满足检测系统响应速度快、定位精度高的要求.     

Engineering design of the double neutral beam injection system for MAST Upgrade

The objectives of the upcoming upgrade to the Mega-Ampere Spherical Tokamak (MAST) require the construction of a new neutral beam injection system. Although the principle of operation is similar to other beamlines including those on JET, the design process is complicated by strict requirements such as the need for intensive ion source commissioning. A double neutral beamline has been designed which satisfies the requirements. This paper reports the engineering design of the MAST Upgrade double beamline, describing the key challenges and unusual solutions adopted.     

箱包DR-CT检测系统中控制子系统的设计与实现

简要介绍了箱包DR-CT检测系统的原理,并详细介绍了其控制系统的功能、硬件结构和软件设计.基于现场总线和无线技术的控制系统运行稳定、可靠,其功能符合设计目标和要求.     

停机不停堆后的风险分析及其控制措施探讨

根据机组实际控制中的运行经验和模拟机教学经验,对压水堆核电机组满功率运行时,一旦由于故障,发生停机不停堆后,可能发生的现象和风险进行分析并提出相应的控制措施。     

Study of heat and mass transfers in a spray for containment application: Analysis of the influence of the spray mass flow rate

During the course of a hypothetical accident in a nuclear power plant, spray might be activated in order to reduce static pressure in the containment. The IRSN has developed the TOSQAN experiment to give a better understanding of the heat and mass transfers between a spray and the surrounding confined gas. This article analyses the influence of the injected spray mass flow rate on the thermal-hydraulics of spray tests. The three tests compared in this article, to carry out this analysis, have the same boundary and initial conditions, except the spray mass flow rate ranges from 10 to 53 g s⁻¹. First, the scenario of these three tests used for this analysis and their results are presented. Then, our analysis is focused on the inter-comparison of the thermal-hydraulic behavior induced by spray mass flow rate variations. This inter-comparison is divided into two parts: a global and a local one.     

上海光源X射线针孔相机控制系统设计

采用美国NI公司的PXI-7344运动控制卡对衰减片进行控制;通过RS232协议控制小孔四维移动平台和相机二维移动平台的运动,实现对小孔位置、倾角和相机位置的调节;NI公司的PXI-8252板卡用于1394相机的图像采集.所有控制功能均有机地集成于LabVIEW界面中,实现各部件的协调配合运动,并通过EPICSShar...     

超灵敏小型回旋加速器质谱计外输运装置的工程设计和机械加工

简述SMCAMS外输运装置的工程设计和机械加工.     

Petri-net based modelling approach for ALFRED reactor operation and control system design

In this work, the Petri-net modelling approach applied to the control system design of the Advanced Lead Fast Reactor European Demonstrator (ALFRED) is presented, paying particular attention to the startup procedure. The reactor startup is the operational transient in which all the systems of the plant are brought from the cold shutdown condition to the full power mode, close to load-frequency control. In this phase, the several control actions to be taken need to be properly coordinated. To this end, the operational sequence which constitutes the reactor startup procedure has been described by adopting the Petri-nets approach, i.e., a useful formalism for the modelling and the analysis of Discrete Event Systems. Thanks to this quantitative representation, it is possible to easily derive the corresponding control scheme. In addition, the Petri-nets approach has been also exploited for the two-level control system architecture, namely a master system coordinates the operation of the plant by sending suitable signals to the slave system, in which feedback controllers are implemented. As a major outcome of this work, the procedure for the reactor startup and the transition to the full power mode has been simulated in order to assess the control system performance.     

Active control system upgrade design for lower hybrid current drive system on Alcator C-Mod

As a part of the scheduled expansion of the Alcator C-Mod lower hybrid current drive (LHCD) system from 12 to 16 klystrons to accommodate installation of a second LH antenna, the active control system (ACS) is being redesigned to accommodate the additional klystrons. Digitizers and output modules will be cPCI modules provided by D-tAcq Solutions. The real-time application will run on a standard PC server running Linux. Initially, the new ACS system will be designed to control 8 klystrons on the second LH antenna and the existing ACS will control the remaining 8 klystrons on the existing LH antenna. Experience gained operating the existing LHCD system has given us insight into the design of a more robust, compact, efficient and simple system for the new ACS. The design upgrade will be patterned on the digital plasma control system (DPCS [1]) in use on C-Mod.     

TMSR核功率控制系统的PID设计与仿真

功率控制系统(Power Control System,PCS)是反应堆控制系统(Reactor Control System,RCS)的重要组成部分,它完成功率提升、功率保持与功率调节的作用。在钍基熔盐堆(Thorium Molten Salt Reactor,TMSR)核能系统固态堆设计方案中,功率控制器根据实测功率与设定功率值之间的偏差和偏差的变化趋势,按照经典的比例-积分-微分(Proportional Integral Derivative,PID)控制算法,给出调节控制棒的运动距离和运动方向等信号。PCS的PID算法设计与基于反应堆中子物理、热工及控制棒的传动性能构成的闭环控制系统的特性有关,其不同参数的确定与系统的静态和动态性能指标的要求相对应。本文从控制的角度出发,在已有的控制棒样机中设计的棒控棒位系统及相关中子物理的基础上对PCS的PID算法进行多层次仿真与参数分析,并对系统的可控性与可测性进行分析验证。分析及仿真结果表明两种控制模型下的系统均是完全可控及完全可测的,在合适的PID参数集下均能体现响应的快速性及系统的良好鲁棒性和抗干扰能力,具有实际的应用意义。     

A nodal dynamic model for control system design and simulation of an MHTGR core

The modular high-temperature gas-cooled nuclear reactor (MHTGR) is seen as one of the best candidates for the next generation of nuclear power plants. China began to research the MHTGR technology at the end of the 1970s, and a 10 MWth pebble-bed high-temperature reactor HTR-10 has been built. On the basis of the design and operation of the HTR-10, the high-temperature gas-cooled reactor pebble-bed module (HTR-PM) project is proposed. One of the main differences between the HTR-PM and HTR-10 is that the ratio of height to diameter corresponding to the core of the HTR-PM is much larger than that of the HTR-10. Therefore it is not proper to use the point kinetics based model for control system design and verification. Motivated by this, a nodal neutron kinetics model for the HTR-PM is derived, and the corresponding nodal thermal-hydraulic model is also established. This newly developed nodal model can reflect not only the total or average information but also the distribution information such as the power-distribution as well. Numerical simulation results show that the static precision of the new core model is satisfactory, and the trend of the transient responses is consistent with physical rules.     

Dynamic model for control system design and simulation of a low temperature nuclear reactor

A lumped parameter dynamic model for the primary-loop and the U-tube steam generator of a low temperature power reactor is developed based on the fundamental conservation laws of fluid mass, energy and momentum. The dynamic model is formulated by coupling the point kinetics with reactivity feedback and the thermal-hydraulics of the reactor. The developed dynamic model is implemented on a personal computer using MATLAB/SIMULINK. Numerical simulation results for steady-state and transient responses are then presented, which show that the steady-state precision of the newly developed dynamic model is acceptable and the trend of the transient responses is correct. In addition, the “swell and shrink” behavior of the U-tube steam generator is also verified by numerical simulation. This newly established model can be utilized to control system design and simulation for the low temperature power reactor.     

高温气冷堆核电站示范工程主控室和备用停堆点设计分析

简要概述了华能山东石岛湾核电厂高温气冷堆核电站示范工程(简称HTR-PM)的主控室和备用停堆点的整体设计,着重对主控室和备用停堆点的功能设计、台盘布置、主要作用和特点进行了介绍和分析,为以后的实际工程提供参考。     

Probabilistic methodology for turbine missile risk analysis

A methodology has been developed for estimation of the probabilities of turbine-generated missile damage to nuclear power plant structures and systems. Mathematical models of the missile generation, transport, and impact events have been developed and sequenced to form an integrated turbine missile simulation methodology. Probabilistic Monte Carlo techniques are used to estimate the plant impact and damage probabilities. The methodology has been coded in the TURMIS computer code to facilitate numerical analysis and plant-specific turbine missile probability assessments. Sensitivity analyses have been performed on both the individual models and the integrated methodology, and probabilities have been estimated for a hypothetical nuclear power plant case study.