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2011年核能行业仿真技术及应用研讨会会议简介(2011.7.7-2011.7.8)
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2011年7月7-8日，“2011核能行业仿真技术及应用研讨会”在北京召开。本次会议由中国核能行业协会主办，中科华核电技术研究院承办、中广核（北京）仿真技术有限公司协办。来自环保部核与辐射安全中心、核能协会、相关核电集团公司、核电厂营运单位、研究设计院所、高校、设备制造厂等42家单位的100多位专家参加了研讨。中国工程院院士李伯虎等22名专家作了专题技术报告。与会专家围绕我国核能行业仿真技术的发展现状，关键技术研究、管理、发展趋势，系统建模与仿真，集成测试技术等议题，展开了热烈讨论和交流，分享了行业内仿真技术的最新成果。本次会议共收录论文72篇。
本次会议论文情况如下：
序号 论文名称 论文作者 单位 1 AP1000全范围模拟机特点分析 AP1000全范围模拟机特点分析 山东核电有限公司 摘要：介绍了AP1000全范围模拟机的整体架构、工艺系统仿真，着重分析介绍了使用翻译器对实际电厂仪控组态文件进行转换，实现仪控仿真的步骤；与其他仪控仿真模式进行了对比，就各自的优缺点进行分析。
关键词：AP1000；模拟机；仪控；虚拟实物模拟；全模拟
Abstract：This article introduces AP1000 simulator architecture and process system simulation. Particular, it analyzes an advance translation mode which use translator to generate control code from actual plant I&C builder files. This article compares the advantage and disadvantage with other I&C simulation mode.
Keywords：AP1000；I&C；Emulation；Full Simulation2 核电数字化仪控系统的仿真方法与实施方案探讨 吴毅，王晓星，胡晓亮，庄进，曹晖 中广核工程有限公司 摘要：结合目前几个新建在建核电机组全范围仿真机中对核电数字化仪控系统（或集散式控制系统）的仿真方法及工程实施方案，本文重点分析和探讨参考机组采用DCS后，如何针对核电DCS特点及核电机组仿真机质量与进度要求，选择恰当的仿真技术方法，并从实际工程实施、性能及运行维护等多个角度，对几种可能的仿真方法及实施方案的优缺点进行分析比较，以便今后根据不同实际情况，为选择最合适的仿真方法及实施方案提供参考。 3 快堆工程仿真机开发的探讨 郑剑香，黄建华 厦门大学能源研究院 摘要：随着仿真技术的不断发展，人们已能通过对核能系统的建模、仿真，开展核能系统的研发工作。工程仿真机是非常有效的核能系统开发的工具，包括反应堆系统设计、工程研究、安全分析、运行支持和辅助培训等。建模与仿真技术将在核能发展中扮演重要角色。
本文探讨快堆工程仿真机的建模、仿真开发技术。文章将介绍轻水堆工程仿真机所采用的仿真开发技术，轻水堆和快堆在堆芯、热工水力等方面仿真技术差异比较，以及快堆工程仿真机开发拟采用技术方法的初步探讨。
关键词：快堆；建模；仿真
Abstract：With continuous development in simulation technology, research and development of nuclear energy systems can be performed through modeling and simulation of these systems. Multi-function Engineering Simulator can be a very effective tool in the development of nuclear energy systems, including reactor design, engineering, safety analysis, operational support and supplemental training. Modeling and simulation technology will play an important role in the development of nuclear energy.
This paper explores utilizing modeling and simulation technologies in the development of fast reactor engineering simulator. It looks at modeling and simulation technologies used in light-water reactor engineering simulator, and reviews the main differences between light-water reactors and fast reactors in areas such as the reactor core, thermal hydraulics, etc., and proposes preliminary technical methods to be used in the development of fast reactor engineering simulator.
Keywords：Fast Reactor；Modeling；Simulation4 红沿河一期全范围模拟机的设计和开发 毛伟，孙明军，李永权，徐毅伟，袁淑玲，张琰，陈伟 毛伟，孙明军，李永权，徐毅伟，袁淑玲，张琰，陈伟 摘要：模拟机做为核电站操作人员进行培训的必备工具是电站生产准备期间的关键路径。红沿河核电站模拟机做为国内首个采用自主化DCS建设的设备其设计有着自身的特点，其开发经验对于后续同类电站的模拟机建设有着一定的参考意义。本文就模拟机供货商的设计和开发流程进行了阐述，并就模拟机测试取得的经验进行了介绍。为从事模拟机制造、测试和管理工作的人员提供参考。
关键词：仿真；模拟；DCS
Abstract: Simulator is an essential tool in nuclear power plant for operator training and it is also ctitical node in preparing for the plant running. Hongyanhe Nuclear Power Plant Simulator has its own characteristics of its design, the development experience for the subsequent construction of similar power plant simulator has certain reference significance. The design and development process of simulator are described, and the test experience was introduced.It provide reference for the manufacturing, testing and management staff.
Keywords：Simulator；Development；Design5 三代核电机组全范围模拟机技术探讨 顾文革 国核自仪系统工程有限公司 摘要：随着三代核电的发展，对全范围培训用模拟机的需求增加，如何适应核电特点、
制定合理的技术方案，成为摆在模拟机技术研究者面前的课题。本文总结了国际上核电模拟
机技术发展的现状；结合三代核电在我国的发展，分析了三代核电全范围模拟机的技术方案
及其特点；提出了三代核电全范围模拟机的选型方案。
关键词：模拟机；仿真技术；数字化仪控系统；三代核电6 核电厂全范围培训模拟机维护策略探讨 卢明贤 卢明贤 摘要：本文从秦山300MWe核电机组全范围模拟机的维护管理实例出发，多角度介绍模拟机维护的主要工作内容，并给出了对于每类维护任务的应对策略；总结出几类全范围培训模拟机的维护模式，旨在探讨一种能普遍适用的维护模式，特别是针对多台模拟机的统一维护提出一种建议方案，为新建核电厂全范围培训模拟机的维护管理提供参考或拷贝，达到规范管理。
关键词：全范围模拟机；自主维护；外委维护
Abstract: The paper takes Qinshan 300MWe Full scope simulator as an example, introduces the main maintenance tasks of training simulator, and provides the maintenance methods to each kind of task. The purpose of this paper is to explore a maintenance mode that applies to most simulators. The paper also provides some suggestions for reference to newly-built simulators.
Key words: Training Simulator；Maintained by internal force；Maintained by external force7 高温气冷堆核电站示范工程全范围模拟机监造管理浅析 郭鹏飞 华能山东石岛湾核电有限公司 摘要：通过对核电站全范围模拟机的简要介绍，分析了对高温气冷堆核电站示范工程全范围模拟机项目进行驻厂监造的必要性以及全范围模拟机监造管理的基本工作，从而阐明了业主对供货方的高度控制能力、完善的管理程序和全方位的积极影响是示范工程全范围模拟机按时高质量完成的有力保障。
关键词：高温气冷堆；全范围模拟机；监造8 浅谈建立量化的核电模拟机项目管理 孙远志，吴帆 孙远志，吴帆 摘要：文章分析了核电模拟机项目特点，阐述了创建WBS是实现量化管理的基础，基于WBS，制定项目的进度、成本基准，确定质量目标.使用范围变更统计量、挣值分析参数以及DR统计量对项目实施量化管理，实现整个项目过程的可视化。
关键词： WBS；挣值分析；DR管理；PMP；项目管理；核电模拟机
Abstract: This article analyzed the particularity of simulator project in Nuclear Power Station, expound that a realizable WBS is the basis of whole quantitative management. Base on WBS, Project team can create baselines for schedule and Cost, object for quality. Project team use Scope Change Statistic, Earn Value Management and DR statistic to implement quantitative management which can make project control visible.
Keywords：WBS；Earn Value Management；DR Management；PMP；Project Control；Simulator9 CPR1000全范围模拟机与工程设计验证模拟机性能分析 赵岩峰，苏朝葵，张焕欣，田颖，廖惜民 深圳中广核工程设计有限公司仪控所 摘要：本文针对核电站全范围模拟机和工程设计验证模拟机的特点，从功能定位、模拟范围、实现方式、性能指标、经济性等方面对两者的异同进行研究分析，为模拟机的配臵优化提出参考建议。
关键词：核电站；工程设计模拟机；全范围模拟机
Abstract: Aiming at the full-scope simulator and engineering design verification simulator‗s characteristic , the paper study and analyze the difference between them on the function, simulation scope, implementation, performance, economic, and so on. And give the reference for simulator‘s configuration optimized.
Keywords: Nuclear power plant; Design verification simulator; Full scope simulator10 红沿河模拟机仿真方式 袁淑玲，孙明军，李永权，郝俊慧，侯余生，王惠杰，徐毅伟 辽宁红沿河核电有限公司 摘要：模拟机作为核电站持照人员的培训以及电厂控制变更的重要设施，在核电站运行准备中起到关键作用，由于每个电站采用的技术有所差别，模拟机的仿真过程和方式也随之有所不同，红沿河模拟机采用了多种仿真方式，引进了先进的仿真技术，为模拟机制造的国产化奠定了基础。本文就红沿河核电站的仿真形式进行展开详述，讨论模拟机仿真方式的种类及其对模拟机质量产生的影响，为后续模拟机项目提供参考。
关键字：仿真；模拟；DCS
Abstract: The simulator is one of the important equipment in nuclear power plant for operator training and changing the plant controlling. It plays the key role in preparing for the plant running. Because each power plant uses different technologies from the others, so the process of simulating will be different. We used many methods to simulate our plant, it induced the advanced technique from other country and laid the foundation for making simulator by ourselves. According to the simulation form of HYH nuclear power plant, this article will discuss the simulation ways and its influences to the simulator quality, hoping it could provide some references for the following simulator projects.
Key words：Emulate；Simulate；Distribute Control System11 核电模拟机监控新技术在红沿河项目中的应用 徐毅伟，孙明军，毛伟，李永权，连燕芬，侯余生，张琰，陈伟 辽宁红沿河核电有限公司 摘要：本文介绍了红沿河核电站全范围模拟机监控系统的应用和主要原理，讨论其实现的方法及技术要求。
关键词：模拟机；监控；声像监控系统；DCS多画面监控；远程监控；软件开发；教控室；DCS
Abstract: This paper introduces the main principle about Monitoring and Control System of full scope simulator for Hongyanhe Nuclear Power Plant, to discuss implementation methods and technical requirements.
Keywords: Simulator；Monitoring；Audio and Video Monitoring System；DCS Multi-screen Monitor；Remote Monitoring；Software Development；Teaching Control Room；DCS12 台山核电第一台EPR模拟机实施策略及技术特点 崔浩，邱学彬，朱德龙 台山核电合营有限公司 摘要：台山核电为了消除EPR机组建设中模拟机培训方面存在的风险，特引进了参考机组法国FA3核电站第三阶段模拟机，为了实现早培训、早接触、早消化的方案，合同执行时先从第二阶段拷贝引进。本文重点介绍法国FA3模拟机的研发过程和台山第一台EPR模拟机引进具体实施策略、阶段验收测试、模拟平台的技术和设备配臵特点、课程引进和开发等内容。
关键词：EPR；FSS；TFS；仿真方式；激励方式；虚拟方式；I&C；HMI；软表盘；ALICES
Abstract：Taishan nuclear power joint venture company(TNPJVC) purchased FA3 phase 3 simulator In order to eliminate the risk of full scope simulator delay. Taishan nuclear power plant refers to FA3 and installed FA3 phase 2 simulator for earlier training, earlier contact and earlier mastering. The main task and contribution of this paper expatiates French FA3 simulator developing progress and Specific Strategy Implementation of Taishan nuclear power plant first simulator, pahse test and accepting, technique and configure of simulator form plant, training course indraught and developing comment.
Keywords：EPR；FSS；TFS；Simulation；Stimulation；Emulation；I&C；HMI；Soft Dial；ALICES13 秦山二期1#模拟机改造 秦山二期1#模拟机改造 中核集团核电秦山联营有限公司 摘要：本文介绍了秦山二期模拟机改造项目，包括硬件改造和软件改造的相关内容，其中硬件改造中接口系统、配电系统以及特殊仪表等得改造是项目中的亮点，软件改造中的就地操纵员站、新教控台以及DCS仿真软件开发也有多个创新点，文中对这些内容进行了详细说明。
关键字：模拟机；就地操纵员站；教控台14 核电站模拟机维护经验浅谈 兰志斌 中广核（北京）仿真技术有限公司 摘要：本文结合在建核电站全范围模拟机维护工作,探讨制定科学、合理、可行的维护策略和方式方法,做到预防性维护、日常维护、故障维护紧密配合,对模拟机进行系统的、有计划的、定期的维护，对于提高全范围模拟机的可用率,保障核电站模拟机正常培训具有积极的借鉴作用。
关键词：核电；仿真；维护经验15 核电站全范围模拟机虚拟DCS分包管理初探 雷 静 中广核（北京）仿真技术有限公司 摘要：随着中国核电事业的飞速发展，目前核电仿真行业已进入全面国产化阶段。中广核（北京）仿真技术有限公司，作为国内首台自主化百万千瓦级核电站全范围模拟机的开发商，在模拟机项目管理以及分包商管理的领域累积了不少经验。本文旨在于对宁德项目对外分包管理经验进行总结，以期对后续项目管理工作提供借鉴。同时，本文对将来的分包管理发展方向以及管理模式进行了展望。
关键词：仿真机；分包管理
Abstract：With the fast development of Chinese nuclear power industry, nuclear power simulation industry has entered into the comprehensive localization stage at the present stage. CNPSC, as the developer of the first million kilowatt grade full scope simulator in China, obtained some experiences at FSS project management and sub-contract management. The article aims to summarize the experiences of the project management and sub-contract management and to improve subsequent projects. In addition, this article looks into the distance for sub-contract management development direction and management mode.
KeyWords: Simulator；Sub-contract16 核电仿真技术的发展 林克军 中广核（北京）仿真技术有限公司 摘要：本文从计算机的硬件，系统软件，编程技术的角度，描述了仿真技术的发展，并重点描述现在的仿真技术的特点，着重描述了图形化的建模和面向对象的编程技术。
关键字：核电仿真；仿真平台；建模；模拟机；在线修改
Abstract：It describes how the computer technology in hardware, operating system and programming influences the advancement of simulation technology. The feature of the current simulation technology is presented and the Drag and Drop modeling and Object-oriented technology is highlighted.
Keywords：Nuclear Power Simulation； Object-oriented programming；modeling, simulator；Online-editing17 三门AP1000全范围模拟机BEACON系统的仿真实现 庄文翠 三门核电有限公司 摘要： 本文介绍了AP1000三门核电站反应堆堆芯运行最佳评估分析系统BEACON的系统功能，详细描述了全范围模拟机中该系统的仿真过程，以及使用的简化和假设，最后对仿真结果进行分析，认为BEACON的仿真模型能够满足培训要求。
关键词： 三门核电厂；AP1000；全范围模拟机；BEACON；仿真
Abstract: This paper describes the function of BEACON system for AP1000 Sanmen Nuclear Power Plant, provide detailed introduction of the BEACON simulation in Sanmen Full Scope Simulator, and simplification and assumption applied during simulation, analyses the result，concludes that simulation of BEACON satisfy training requirement.
Keywords: Sanmen nuclear power plant；AP1000；Full scope simulator；BEACON；Simulation18 CPR1000型核电站工程模拟器热工模型的开发与扩展 熊义强, 林萌，侯东，龚湛 上海交通大学核科学与工程学院 摘要：为使核电站工程模拟器能够尽快投入使用，本文首先建立了反应堆主系统热工模型，并以此对岭澳二期核电站给水泵双重故障进行了计算分析。然后在工程模拟器后期开发中，通过多个两流体程序耦合的方式，对一回路主系统模型进行了扩展，主要包括辅助系统和二回路等系统模型的纳入，并以此进行了仿真计算。结果表明，早期的模型可以很好的计算给水泵双重故障对反应堆运行的影响，扩展后的热工模型能够很好的计算瞬态过程，增加了模拟器的仿真范围和精度。
关键词： 主系统；模型扩展；耦合；工程模拟器
Abstract： In order to put nuclear power station engineering simulator into use as soon as possible, reactor primary system thermal model is established, and double failures of feedwater pump at Ling Ao Nuclear Power Station Phase II are calculated and analyzed by the model. Then in the late development of engineering simulator, the main system model is extended in the way of multiple two-fluid codes coupling, including auxiliary systems and secondary circuit systems models and so on which are added into the main system model, and the simulation based on this is carried out. The results show that the earlier model can well calculate the impact of reactor operation caused by double failures of feedwater pump, the extended thermal model can well calculate transient processes, and increases simulation scope and accuracy of the engineering simulator.
Key words：Main system; Model extension; Coupling; Simulation; Engineering simulator19 核反应堆动力学点堆模型处理中值得注意的问题 王远隆 中国核动力研究设计院核反应堆系统设计技术重点实验室 摘要： 本文针对在计算机仿真实验中如何处理核反应堆动力学点堆模型的方法问题进行了对比分析。通过分析提出了认定点堆模型处理合理性的基本原则。这样的原则具有实际的工程使用价值。
关键词：核反应堆动力学；点堆模型；计算机仿真
Abstract：This paper provides the comparative analysis on how to process the point_reactor model of nuclear reactor dynamics in computer simulation test. Through the analysis, the basic principles are given here that can be used for determining reasonable degree on processing the point_reactor model. These principles are the important guide on using the point_reactor model in the nuclear reactor engineering.
Key words：Nuclear reactor dynamics；Point_reactor model；Computer simulation20 秦山三期全范围模拟机增设辅助给水泵的模型软件变更 蔡根祥，莫银良 秦山第三核电有限公司 摘要: 全范围模拟机实现了对电厂系统和设备的功能模拟。本文对秦山三期全范围模拟机的结构和电厂系统或设备的模拟方式进行了介绍，讨论了电厂系统建模的原理和实现方法。本文通过工艺系统流网、控制设备和控制逻辑三个部分对全范围模拟机增设辅助给水泵的模型软件变更进行介绍，并对变更实施的效果进行了分析和评估。
关键词：核电厂系统建模；模型软件变更；新增辅助给水泵
Abstract：The Full Scope Simulator realizes the functional simulation of various systems and equipments in the Nuclear Power Plant. The paper briefly introduces the structure of the TQNPC‘s Full Scope Simulator and the simulation technique applied, and specifies the principles and implementation of systems modeling. The paper discusses the modification of modeling software for a newly added auxiliary boiler feedwater pump from the perspectives of process system, equipment control and logic. The impacts of the modification to the simulator are also analyzed and assessed in this paper.
Keywords: Nuclear Power Plant (NPP) Systems Modeling；Modification of Modeling Software；New Auxiliary Boiler Feedwater Pump21 HTR-PM非能动余热排出系统仿真分析 周树勇1，王俊三1，康晓京2 1．中广核（北京）仿真技术有限公司
2.中核能源科技有限公司摘要：非能动余热排出系统是球床模块式高温气冷堆电站（HTR-PM）的重要特点，其能在事故工况下通过自然循环导出堆芯剩余发热。本文采用3KEYMASTER仿真平台的FlowBase建模工具对HTR-PM非能动余热排出系统进行了仿真研究，分析计算了非能动余热排出系统在正常工况和事故工况下的工作能力。分析结果表明：非能动余热排出系统能有效地导出堆芯余热，计算结果与设计计算值误差较小，建立的仿真模型可行，适用于HTR-PM非能动余热排出系统的实时仿真。
关键词：非能动余热排出系统；HTR-PM；3KEYMASTER；FlowBase；自然循环
Abstract：The passive emergency heat removed system, with which the decay heat can be removed from the reactor core in accidental condition by means of natural circulation, is an important characteristic of the Pebble-bed Modular High-Temperature Gas-cooled Reactor (HTR-PM). Based on the preliminary design of the HTR-PM, the simulation of the passive emergency heat removed system (PHRS) was studied by the help of 3KEYMASTER FlowBase Hydraulic Modeling Tool. Some important parameters were analyzed in order to evaluate the heat removal capacity of the PHRS in normal and accidental conditions. The calculated results show that, the PHRS works effectively. The model is feasible and has high precision.
Keywords：Passive emergency heat removed system；HTR-PM；3KEYMASTER；FlowBase；Natural circulation22 HTR-ESS 中的堆芯物理仿真方法 魏春琳，眭喆，孙俊，单文志 清华大学核能与新能源技术研究院 摘要：本文对高温气冷堆工程模拟仿真系统（简称HTR-ESS）中使用的反应堆堆芯物理计算仿真方法进行介绍。为了满足模拟机中实时的要求，研究开发三维圆柱几何堆芯多群中子时空动力学改进准静态方法模拟计算程序，使中子动力学程序满足模拟过程的实时要求。模型中提出利用拟合公式计算宏观截面，使截面可以实时反应出堆芯状态，可以与堆芯热工形成反馈。堆芯中的控制棒使用等效吸收体进行替代，最后给出了一张控制棒动作引起的功率变化最终稳定的计算结果，结果显示，建立的堆芯物理实时计算模型是满足设计条件和要求的。
关键词：HTR-ESS；时空动力学方程；改进准静态方法；宏观截面；控制棒
Abstract：A calculation model on reactor physics is set in this article. 3D cylinder reactor core neutron space time kinetics is simulated with an improved quasi static method. This method can solve the kinetics equation in real time. Macro-section used in model is calculated from a fitting equation. This equation make the sections can reflect the reactor state and make the model can be related with reactor thermal hydraulics. The control rod in reactor is instead of effective absorber. In the end of the article, the changes as a result of the action of control rods are shown. Established real-time calculation model for the reactor physics meet the design requirements.
Keywords：HTR-ESS；Space time kinetics equation；Improved quasi static method；Macro section；
Control rods23 利用模拟机平台进行高温堆设计 孙俊，眭喆，马远乐，郑艳华 清华大学核能与新能源技术研究院 摘要：反应堆模拟机具有友好的人机界面，在满足实时性要求时会牺牲一定的数值精度，部分参数往往通过已知工况反算得到，无法进行设计计算。传统的反应堆系统分析软件包含可靠的物理模型和参数，可以进行设计和事故分析，但普遍缺乏较好的前后处理技术和图形操作界面。本文尝试综合模拟机平台技术与反应堆设计软件的优势，利用vPower模拟机平台对高温气冷堆堆芯流动现象进行图形化建模，根据真实的物理模型和参数对平台中的模块进行二次开发，以适应于堆芯流动与压降的设计与分析，并利用平台求解器对建立的流体网络模型进行求解。初步的计算结果与高温气冷堆设计软件THERMIX有较好的对比，在一定程度上说明了利用模拟机平台技术开展反应堆设计的可行性。
关键词：模拟机；反应堆设计；二次开发；高温气冷堆
Abstract：The reactor simulators are designed with friendly human-machine interface. According the real-time requirement, the models in simulators are less accurate and some parameters need to be determined by back calculations. Therefore, simulators may be not proper for designing a reactor. Traditional reactor system analysis software has much more accurate and reliable models and parameters in designing and accidental analysis, but is usually lack of good pre- and post-processing, as well as visualization of the reactor data. In this paper, the advantages of simulators and design software were combined for the core flow analysis in high temperature gas-cooled reactor. The vPower platform, a simulator platform, was used to build the flow network in the graphic interface, in which, the modules for calculating the flow resistance and pressure drop were second developed and strictly according to formula and expressions from the design software THERMIX. Using the flow network solver in the platform, the preliminary test results agreed well with the THERMIX data. Therefore, the ability of the simulator platform was present in designing and analyzing the reactor.
Keywords：Simulator；Reactor design；Second development；HTGR24 基于labview蒸发器水位的建模与仿真 付敏，邱建文，蒋明瑜，林日中 付敏，邱建文，蒋明瑜，林日中 摘要：本文通过对核电厂蒸汽发生器的功能，水位测量与控制的理解，确定蒸发器水位仿真模型，并在labview软件平台实现该模型。为了考察该仿真模型的正确性，将运行有该仿真模型的PXI虚拟仪器设备与已建立的蒸发器水位控制系统的接口相连接构成闭环，运行该闭环系统，通过几种工况的运行证实该仿真模型的正确性。
关键字：蒸汽发生器；蒸发器水位仿真模型；labview软件；工况
Abstract：This article determine the evaporator water level simulation model by the function of nuclear steam generator, water level control,and realize this model in labview software platform. In order to examine the correctness of this simulation model, will run the simulation model.Through several operation modes it is confirmed the correctness of this simulation model.
Keywords：Evaporator water level simulation model；Steam generator；Labview software；Operation25 FLOWBASE在核电站除氧器仿真计算中的应用 王芋丁，王俊三，许文朝，康晓京 中广核仿真技术有限公司
中核能源科技有限公司摘要：除氧器是核电站常规岛的一个重要设备，由于它内部的流动包含了汽相和液相，因此其内部的动态仿真计算相对复杂。FLOWBASE作为一个流体网络仿真计算软件，可以精确地模拟除氧器在核电站全工况范围下的动态过程, 同时其建模方式非常直观，方便，通用性很好。本文将其用于实际的1000MW压水堆核电站除氧器的仿真计算，并对各个工况下的仿真计算结果进行了分析，验证了FLOWBASE在核电站除氧器仿真计算中的准确性。
关键词：除氧器；仿真；模型；建模；FLOWBASE
Abstract: Deaerator is an important device of nuclear power plant Conventional Island. The dynamic simulation of the inside flow is complex because it includes the flow of both vapor and liquid. As Fluid network simulation software, FLOWBASE can accurately simulate the dynamic process of the deaerator under full working condition of the nuclear power plan. The modeling method is visualized, convenient and has excellent versatility. In this paper, the deaerator of a real 1000MW pressurized water reactor power plant is simulated by FLOWBASE. And the simulation results of each working condition are also analyzed. The simulation results verify FLOWBASE's accuracy in simulation of deaerator in nuclear power plant.
Keywords：Deaerator；Simulation；Model；Modeling；Flowbase26 基于RELAP5-3D的压水堆稳压器建模与仿真 姜夏岚，王江，秦治国 中广核（北京）仿真技术有限公司 摘要：本文通过对CPR1000堆型压水堆核电站的稳压器实际运行特性进行分析研究，采用RELAP5-3D程序建立稳压器模型，并模拟了包括加热器、喷淋调节、波动管、稳压器安全阀等压力水位调节系统。同时通过对连续降功率和稳压器安全阀误开启两个工况进行了仿真，结合压力水位调节系统，对稳压器主要参数进行了动态特性分析，并与实际电站的运行特性相比较。结果表明，本模型较高精度的模拟了压水堆稳压器的特性，适用于模拟机教学及其他瞬态分析。
关键词：RELAP5-3D; 压水堆；稳压器；建模；仿真；培训模拟机
Abstract：Based on the research of actual CPR1000 nuclear power plant pressurizer characteristic, an entire pressurizer model with its pressure and level adjustment system, for instance, electrical heaters, spray line, surge line and pressurizer safety valves, is established with RELAP5-3D program. Choosing -5% full power per minute continuous load ramp and inadvertent open one safety valve of pressurizer transients, this article analyzed the pressurizer model dynamic characteristic of main parameters, and compared these with actual power plant data. The result showed that this program and model simulated the pressurizer high realistically and can be used for simulator training and safety analysis.
Keywords：RELAP5-3D；PWR；Pressurizer；Modeling；Simulation；Training simulator28 基于RELAP5的AP1000非能动堆芯冷却系统仿真研究 谭超，单福昌，林旭升，唐雷 中核武汉核电运行技术股份有限公司 摘要：本文采用RELAP5/MOD3.2热工水力仿真程序对AP1000非能动堆芯冷却系统进行仿真模拟，并结合小失水事故中非能动余热排出热交换器、堆芯补水箱、安注箱、自动泄压系统及安全壳内臵换料水箱等各种重要安全设备的瞬态响应和功能实现对模型和仿真程序作出综合评价，为AP1000全范围模拟机研制提供技术基础。
关键词：仿真；RELAP5；非能动；AP1000
Abstract: This paper is the introduction for the simulation of AP1000 passive core cooling system based on RELAP5/MOD3.2. The model and program‘s performance is estimated by the small loss of coolant accident transient considering the function achievement and the instant response of passive residual heat removal exchanger, core makeup tank, accumulator, auto depressurize system and in-containment recirculation water storage tank which are the most important cells of safety related equipments. It is the pre-study for the development of AP1000 full scope simulator.
Key words: simulation, RELAP5, passive, AP100029 HTR-PM主给水系统仿真建模 葛皓 华能山东石岛湾核电有限公司 摘要：HTR-PM全范围模拟机由CNPSC承包，清华大学核研院作为其子承包商负责一回路堆芯物理模型以及堆芯热工模型部分。CNPSC使用图形化建模工具3KeyMaster对核岛辅助系统、常规岛系统以及电气系统进行建模。本文以HTR-PM主给水系统建模为例，对建模和仿真过程进行说明。
关键词：仿真；数学算法；模型；建模；3KeyMaster30 核电厂关键部件运行状态仿真模型的构想 张华德 苏州热工研究院有限公司 摘要: 核电厂大部分设备的部件都是金属材料的,大部分材料都是在高温,高压或强腐蚀环境下使用。对于核岛这个特殊的环境来说,有一些重要的金属材料还会遇到腐蚀和辐照损伤等影响其使用寿命的外部条件。
我们可以尝试在实验室里模拟设备在现场运行的工况,设计加速材料性能实验,在短期内使材料达到一个在现场需要长期才能达到的状态。根据这一系列的实验数据,找出材料结构变化的物理规律,并在计算机上建立仿真模型来反映这些规律,并通过现场实际的检验数据来对这一仿真模型进行修正,以使其能准确的反映设备材料真实的运行状态,预测材料的使用寿命及材料在不同运行参数、运行时间的状态。
关键词：加速实验；仿真实验；计算机仿真；辐照损伤31 PDMS在岭澳二期核电站电缆竖直梯架建模中的应用 贾园，王建朝 中国核电工程有限公司河北分公司 摘要：在三维模型中，电缆路径通过一系列的桥架元件来组成（Pipe、Branch、Components等），电缆敷设时将会用到电缆路径。本文利用PDMS三维设计软件，通过适当的方法用桥架元件来表达电缆路径，对岭澳二期核电站中的电缆竖直梯架元件建模，并分析了一些特殊竖梯的处理方法，该模型在材料统计、检查碰撞和出平面图等应用中取得良好效果。
关键词：核电；PDMS；三维模型；竖直梯架
Abstract: In the three-dimensional model, the cable path is formed with a series of bridge components (Pipe, Branch, Components, etc.), the cable will be used when laying the cable path. In this paper, PDMS is used by the appropriate method to express the cable path bridge components, to set up the model of the cable vertical ladder, and analyze some special cases. the model achieves good results in applications such as statistics in the material ,checking for clashes, and plot plan.
Key words:Nuclear power station；PDMS；Three-dimensional model；Vertical ladder32 基于图形化的汽轮机轴承振动及故障仿真建模分析 张超，郭华，裴宜星，秦治国，潘竟斌 中广核（北京）仿真技术有限公司 摘要： 汽轮机轴承振动是影响汽轮机启动速度及机组安全性的重要因素之一，本文针对汽轮机启动冲转工况搭建了仿真数学模型，拟合出汽机启动工况的特性曲线。并提出多故障触发模型，利用逻辑组态的方法搭建可扩展的多故障模型，并应用到多个项目的汽机监测系统故障设臵中。实践证明，本文的模型能够正确反映仿真对象的全物理过程，具有良好的静态精度和动态响应特性，是具有价值的建模方法。
关键词：汽轮机；轴承振动；故障；仿真建模
Abstract: Steam turbine bearing vibration is one of the factors which affects the speed and security of the power plant. This article has builded the model to simulate the start up operation of steam turbine and fitted the characteristic curve of bearing vibration. This article also proposed the multi-malfunction triggering model which could be expanded using the logical configurations. It has been satisfied the necessary of project training and calculation. The practice has proved that, this model was a valuable modeling method which could reflect the entire physical process of the simulation object correctly and has the good static precision and dynamic response characteristic.
Keywords: Steam turbine；Bearing vibration；Malfunction；Simulation model33 电站真空系统图形化建模仿真 秦治国，姜夏岚 中广核（北京）仿真技术有限公司 摘要: 本文以图形化的仿真平台为基础，通过图形化建模方法对电站真空系统进行模拟，实现了电站真空系统的仿真。目前，该模型已应用于电站仿真机中，仿真结果表明，该算法能够准确有效的仿真真空系统各设备的动态特性且计算速度快，仿真精度高，能够满足工程要求。
关键词: 电站仿真； 真空系统； 图形化建模
Abstracts: With graphical simulation platform as the foundation, through a graphical modeling method to simulate the power vacuum system, and achieve the power vacuum system simulation. Currently, the model has been used in power plant simulator, the simulation results show that not only the simulation algorithm can accurately and effectively simulate the vacuum system dynamic characteristics of the equipment, but also Calculates quickly; the simulation precision is high and meet the project requirements.
KeyWords: Power Plant Simulation；Vacuum System；Graphical Modeling34 核电站辅助变压器分接抽头功能仿真浅析 齐宏伟，钱俊成，裴宜星 中广核（北京）仿真技术有限公司 摘要：本文以3KEYMASTER仿真平台为基础，通过逻辑功能模块对某压水堆核电站辅助变压器分接抽头控制进行逻辑搭建，并通过与虚拟DCS画面的通讯连接，实现了虚拟DCS对辅助变压器分接抽头控制的仿真。目前，该模型已应用于国内某1000MW压水堆核电站模拟机中。仿真结果表明，该逻辑能够满足工程要求和模拟机操作员调节辅助变压器低压侧电压高低变化的培训需求，其模拟方法值得推广。
关键词：变压器；分接抽头；逻辑功能模块；DCS画面35 典型两相流换热器的仿真模拟 郭华，张超，秦治国 中广核（北京）仿真技术有限公司 摘要: 本文基于图形化仿真平台，利用基本图形化模块工具，以核电站重要设备高压加热器为例，根据两相流原理，搭建典型的两相流换热器仿真模型，并应用于核电站二回路整个汽水循环的模拟。模拟结果表明，该模型能够准确实现两相流设备动态特性的仿真模拟，计算结果与实际计算误差小于0.1%，满足工程需要，可以适用于电厂各种工况的工程计算要求。
关键词：仿真；图形化；两相流；高压加热器
Abstract: This article buildes the modal of high pressure heater the important instrument in nuclear power plant established on the graphic simulation platform and basic module tools. This model is based on two phase flow principle and used in steam cycle of the secondary circuit simulation of the plant. The simulation result indicats that, this model could accurately realize two phase current equipment dynamic characteristic simulation, the computed result and the actual computation error is smaller than 0.1%, meets the project needs. The model is suitable for each kind of operating in the power plant calculation request.
Key words: Simulation；Graphical；Two-phase flow；High pressure heat exchanger36 氙毒在反应堆物理仿真中的应用 氙毒在反应堆物理仿真中的应用 中广核（北京）仿真技术有限公司 摘要：本文论述了氙毒的产生和消失过程，分析了氙毒在反应堆停堆以及升降功率等过程中对反应性的重要影响，提出了在反应堆物理仿真中对氙毒的控制方法。
关键词：氙毒；反应堆；仿真；控制
Abstract: This article discusses the producing and reducing procedure of xenon poison, analyses the xenon poison influence on reactivity when reactor shutdown, power increase and power decrease, proposes the way of control for xenon poison in reactor physics simulation.
Key words: Xenon poison；Reactor；Simulation；Control37 用于 HTR-PM 电厂功率调节半实物仿真的实时仿真平台 董哲，黄晓津，张良驹 清华大学核能与新能源技术研究院 摘要：因具有固有安全性，模块式高温气冷堆被视为下一代核能系统的首选堆型之一，功率调节是保证模块式高温气冷堆安全、稳定和高效运行的一项关键技术。在成功设计、建造和运行高温气冷实验堆 HTR-10 的基础上，清华大学核研院目前正在致力于多反应堆模块式高温气冷堆核电站 HTR-PM 开发。由于 HTR-PM 具有两套相互耦合的蒸汽供应系统，从而其功率控制策略不同于具有单反应堆的 HTR-10。因此，为了验证功率调节方案的可行性，就必须构建 HTR-PM 运行特性实时仿真平台，本文介绍了该仿真平台的设计和实现。
关键词：高温气冷堆；功率控制；实时仿真
Abstract: Because of the inherent safety feature, the modular high temperature gas-cooled reactor
(MHTGR) has been seen as one of the best candidates for the next generation of nuclear power
plants. Power-regulation is a key technique to provide safe, stable and efficient operation for the MHTGRs. Based on the successful design and operation of Chinese test high temperature
gas-cooled reactor HTR-10, the high temperature gas cooled reactor pebble-bed module (HTR-PM) project is proposed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua
University. Since HTR-PM is composed of two interconnected nuclear steam supply systems
(NSSS), the power control strategy of the HTR-PM is different from the one-reactor-modular
HTR-10. In order to verify the power regulation strategy for HTR-PM, it is necessary to establish a real-time simulation platform. The design and development of this platform is presented in this paper.
Keywords: High temperature gas-cooled reactor；Power regulation；Real-time simulation38 基于虚拟仪器技术的数字化反应堆保护系统 李炎华，孙娜，谢逸钦，石桂连 李炎华，孙娜，谢逸钦，石桂连 摘要：本文针对核电站数字化反应堆保护系统的特点，研究其验证方法及测试技术，并基于虚拟仪器技术、网络通讯技术及自动化技术，开发出一套验证测试平台，以满足对系统进行功能与性能验证和测试的需求，同时本文对验证测试平台的主要设计方法及功能实现进行了总体介绍，并对其特点进行了总结。
关键字：数字化反应堆保护系统；虚拟仪器；验证测试平台
Abstract: Based on the features of the digital reactor protection system, Validation methods and testing techniques were discussed in this article. By using the virtual instrument technology, network communications technology and automation technology, a verification test platform has been developed to meet the meet the digital reactor protection system‘s functional verification and performance testing requirements. While the primary design approach and function realization of the verification test platform were described, and its characteristics were summarized.
Keywords: Digital reactor protection system；Virtual Instruments；Verification test platform39 数字化仪控TXP系统在田湾核电站模拟机上的成功应用 孙琦 江苏核电有限公司 摘要：文章阐述了田湾核电站数字化仪控TXP系统在全范围模拟机上的仿真实现方式，并介绍了TXP逻辑变更在模拟机上的实现方法；通过实践证明，全范围模拟机可用于仪控逻辑验证功能，具有一定应用前景。
关键字：田湾核电站；TXP系统；仿真；模拟机；逻辑验证
Abstract: The paper describes the simulation of TXP system realized on Full Scope Simulator in Tianwan Nuclear Power Plant and introduces the realization of TXP logic modification on Full Scope Simulator. Proved through practice, the Full Scope Simulator could be used in I&C logic validation and has certain prospect of application.
Keywords: Tianwan Nuclear Power Plant; TXP; Simulation; Full Scope Simulator; Logic validation40 基于acslX软件的AP1000稳压器压力控制系统动态仿真 周韦，马志才 上海核工程研究设计院 摘要：本文针对AP1000稳压器内部传热传质过程的特点，结合西屋AP1000的相关参数，在我院控制系统模型的基础上，对其中稳压器的二区数学模型进行完善和改进，利用acslX软件建立稳压器三区动态数学模型，并严格按照西屋AP1000稳压器的压力控制逻辑，对建立起来的数学模型进行了相应的控制仿真实现。通过比较改进前和改进后模型试验结果与相关设计文件的差异，验证了改进后模型较改进前具有更好的精确性、可扩展性，同时该模型可为今后CAP1400稳压器的仿真工作打下一定基础。
关键字：AP1000；稳压器；控制系统；acslX；仿真
Abstract: According to the characteristics of AP1000 pressurizer dynamic process of Nuclear Power Plant, using AP1000 nuclear plant parameters, a three region model of pressurizer pressure control system for nuclear power plant was established on the base of the SNERDI control system model in this paper, for the purpose of the improvement of the two region model. Simulation experiments have been performed using acslX software according to AP1000 pressurizer pressure control logical diagram. By the comparison between the simulating results and the datas of related design documentation, the result indicates the improved model is accurate and improvable. This model can also lay the foundation for future simulation work of CAP1400 pressurizer.
Key words: AP1000；； Pressurizer； Control system；AcslX；Simulation41 神经网络-PID在蒸汽发生器水位控制中的应用 刘 成，吕会议，王烈林，席发元，袁长迎 西南科技大学 摘要：本文介绍了一种神经网络-PID控制器。它是利用BP神经网络的来实现功率P和PID控制器增益的映射关系。在整个功率范围内，把有限组的PID控制器增益扩展到无穷多组。通过BP神经网络来不断调节PID增益以跟随功率的变化，从而跟踪模型的变化，最后把设计的神经网络-PID控制器应用到蒸汽发生器的水位控制中，在给定的五种工况下得到了很好的仿真结果。
关键词：蒸汽发生器；水位控制；神经网络 PID
Abstract：This paper introduces a Neuro-PID controller control strategy, and applies it to for the steam generator water level control system. At the Neuro-PID control strategy, the BP artificial neural network is exploited to establish a map between the power P and PID gains. The finite sets of PID gains are extended to the possible combinations of PID gains in stable region by mapping. Thus the BP artificial neural network tunes the gains of PID controller to adapt the model changing with the power. The Neuro-PID controllor has been designed and simulated to control the steam generator water level. The simulation results show the favorable performance of the Neuro-PID controller.
Keywords：Steam generator；Water level control；Neuro-PID42 宁德核电站全范围模拟机棒控及棒位系统仿真 李剑，王峰，齐宏伟 中广核仿真技术有限公司 摘要：棒控和棒位系统主要对核电站反应堆温度及功率进行控制，是核电站运行的关键系统之一，其控制的可靠性、精确性直接影响核电站的正常运行，因此也是核电站全范围模拟机开发中需要模拟的重要系统；其仪控部分在该系统的仿真建模中占有很大比重。本文简介了棒控和棒位系统的基本组成，在基于对该系统控制算法分析的基础上，详细介绍了宁德核电站全范围模拟机棒控系统仿真设计方法。
关键字：核电站；全范围模拟机(FSS)；棒控和棒位；仪控(I&C)；仿真
Abstract: In nuclear power plant rod control and rod position system mainly controls the reactor temperature and power. It is one of the key systems in nuclear power plant operating. Its reliability and accuracy directly affects normal operation of the nuclear power plant. So it is important in the development of nuclear power plant full scope simulator(FSS). In the simulation for this system, instrumentation & control (I&C) simulation has a big proportion. In this article we introduced the composing of rod control and rod position system. Based on the analysis of its control principle, we described the simulation of this system FSS for the FSS of Ning De nuclear power plant.
Keywords：Nuclear power plant；Full scope simulator；Rod control and rod position； Instrumentation & Control(I&C)； Simulation43 核电站安全控制系统TXS虚拟机软件 冷杉1，刘纯2，李姝2，程俊杰1，张才科1 1.东南大学能源与环境学院2.中核武汉核电运行技术股份有限公司 摘要：在深入分析大型压水堆核电站数字化仪控系统组合TXP/TXS基础上，为与过程控制系统的TXP虚拟机软件并列应用，本文特别针对核安全控制系统TXS进行虚拟仿真，研发了基于Windows平台的DCS虚拟机软件VTXS（Virtual TXS）。VTXS以自动代码分析和翻译转换为基本构建手段，以Visual C++为集成开发环境，采用面向对象模块化程序设计的方法、多线程和多进程通信的技术，以完全软件形式高逼真度的再现真实TXS系统的安全控制功能。
关键词：核电站；数字化仪控系统；安全控制系统；TXS；DCS虚拟机；仿真
Abstract: On the basic of analyzing digital I&C system TXP/TXS of the large PWR nuclear power plant deeply,in order to coordinate with process control system TXP, this paper specially takes safety control system TXS as the simulation object, and designs and develops DCS virtual machine software VTXS(Virtual TXS) on the platform of Windows. Adopting the method of object-oriented modeling and modularization program design, using technologies such as multithreading and multi-process-communication, by the basic way of automatic code analysis and data code translation and with Visual C++ platform as the developing environment, VTXS recreates the functions about safety control of real TXS with high fidelity in the form of software.
Key words: Nuclear power plant；Digital I&C system；Safety control system；TXS, DCS virtual machine；SimulationAbstract: On the basic of analyzing digital I&C system TXP/TXS of the large PWR nuclear power plant deeply,in order to coordinate with process control system TXP, this paper specially takes safety control system TXS as the simulation object, and designs and develops DCS virtual machine software VTXS(Virtual TXS) on the platform of Windows. Adopting the method of object-oriented modeling and modularization program design, using technologies such as multithreading and multi-process-communication, by the basic way of automatic code analysis and data code translation and with Visual C++ platform as the developing environment, VTXS recreates the functions about safety control of real TXS with high fidelity in the form of software.
Key words: Nuclear power plant；Digital I&C system；Safety control system；TXS, DCS virtual machine；SimulationAbstract: On the basic of analyzing digital I&C system TXP/TXS of the large PWR nuclear power plant deeply,in order to coordinate with process control system TXP, this paper specially takes safety control system TXS as the simulation object, and designs and develops DCS virtual machine software VTXS(Virtual TXS) on the platform of Windows. Adopting the method of object-oriented modeling and modularization program design, using technologies such as multithreading and multi-process-communication, by the basic way of automatic code analysis and data code translation and with Visual C++ platform as the developing environment, VTXS recreates the functions about safety control of real TXS with high fidelity in the form of software.
Key words: Nuclear power plant；Digital I&C system；Safety control system；TXS, DCS virtual machine；Simulation44 高温气冷堆工程模拟机的控制系统仿真研究 姚启欣，梁艳明，眭喆 中核能源科技有限公司 摘要: 控制系统仿真是高温气冷堆工程模拟机(ESS)项目的重要研究内容。控制系统仿真的目标是模拟参考电站(高温气冷堆示范电站HTR-PM)DCS系统功能，使模拟机能够在操作员控制下的进入各种运行工况，实现堆芯核心模型的验证、参考电站运行特性的研究等功能。本文阐述控制系统仿真的总体设计和实施方法，并简要介绍算法库、图形库的设计和组态方法。
Abstract: Control system simulation is an important component of HTR ESS research. Its purpose is to simulate the functioning of the DCS of the reference power plant (HTR-PM). With it, ESS can be controlled by operators to enter different running states, so that the model of reactor core can be testified, and the performance characteristic of the reference power plant can be researched into. The paper illustrates the architectural design and the execution plan of control system simulation, and it also briefly introduces the design of the algorithms library, the graphic library as well as the method of logic configuration.45 核电站常规岛汽机控制系统翻译仿真方案研究 王峰，李剑，印勇 中广核仿真技术有限公司 摘要：本文就核电站仪控系统中汽轮机的控制系统仿真方法展开研究，以宁德核电一期全范围模拟机项目中TG控制系统仿真方案为例，简要介绍了项目实施过程中对ALSTOM P320控制系统的仿真模拟方案和实施过程，可作为核电站全范围模拟机的设计参考文件。
关键字：核电站；全范围模拟机(FSS)；棒位棒控；仪控(I&C)；仿真
Abstract: In nuclear power plant turbine control and protection system controls power of the plant. It is one of the most important systems of conventional island in nuclear power plant operating. Here we introduce the simulation of these control system in full scope simulation system by case of NINGDE nuclear power station. Give the basic idea of translation method of simulation. Can be use for the reference of simulation of FSS.
Keywords：Nuclear power plant；Full scope simulator；Simulation46 核电全范围模拟机教控台就地图画面设计与开发 杨政理，林克军 中广核仿真技术有限公司 摘要：本文介绍了国产百万千瓦级核电站全范围模拟机教练员工作站（本文简称：教控台）就地图画面的设计与开发过程，探讨就地图画面设计中的一般性原则，使教控台就地图界面友好、功能丰富、操作方便，最大程度地满足模拟机培训的需求。
关键词：核电模拟机；教控台；就地图
Abstracts：This article describes the design of Instructor Station P&ID diagram in the Full Scope Simulator for 1000MWe Nuclear Power Plants in China, and the general rules that it follows so that the display is friendly and beautiful.
Key Words：NPP Full-scope Simulator；Instructor Station；P&ID47 基于DCS Emulation方案的Replay功能实现机理浅析 刘宁宁，潘超祥 中广核工程有限公司设备采购与成套中心 摘要：本文以某核电站所配全范围模拟机为例，通过分析其Replay功能实现过程，介绍了基于DCS Emulation方案的核电站全范围模拟机Replay功能的实现机理，为了解模拟机及模拟机的运行、维护奠定了理论基础。
关键词：核电站；全范围模拟机；Emulation；Replay；实现机理
Abstract： Replay is one basic function of simulator. In this paper, the full scope simulator for a nuclear power station is taken as an example, by means of analysis on the implementation process of Replay, mechanism of DCS Emulation solution-based Replay function is introduced. The theoretical foundation is laid to realize simulator and run/maintain simulator.
Keywords：Nuclear power station；Full scope simulator；Emulation；Replay；Implement mechanism48 核电站安全级虚拟控制系统的设计开发 黎知行，章旋，钟俊 中广核仿真技术有限公司 摘要：以三菱MELTAC system数字化仪控系统为虚拟对象，采用先进的虚拟DCS技术，在3KeyMaster仿真平台上设计和开发具有高逼真度的虚拟控制系统软件，实现在模拟机中对安全级DCS系统的Level1控制层逻辑的全仿真，应用于运行人员和热控人员的培训、系统控制策略的优化和系统故障模拟诊断。
关键词：虚拟DCS；3KeyMaster；功能块；智能转换；面向对象
Abstract：Taking digital control systems of Mitsubishi Electric METAC as the simulation object, Visual control systems software based on advanced visual DCS technology was designed and developed on 3KeyMaster‘s platform. It realizes the wide simulation of simulator safety DCS Level1 control logic level and applies to training operators and engineers,optimizing the control strategies and diagnosing the system fault.
Keywords：Visual DCS；3KeyMaster, Function Bock；Intelligent transition；Object-orientation49 核电站数字化仪控系统电磁兼容仿真预测技术的研究 杨凯生，张春雷，金成日 北京广利核系统工程有限公司 摘要：本文引述了核电站仪控系统电磁兼容的重要性，通过介绍电磁兼容技术发展的趋势，提出了电磁兼容仿真预测在核电站数字化仪控系统设计过程中的应用理论，说明电磁兼容仿真预测对提高数字化仪控系统的电磁兼容可靠性有重要意义。
关键词：电磁兼容仿真；数字化仪控系统
Abstract：This article quotes the Electro Magnetic Compatibility (EMC) importance of instrumentation and control (I&C) systems in nuclear power plant. According to the development directions of EMC design method, the article gives EMC simulation application theory in the process of designing digital I&C systems in nuclear power plant. It shows significance that EMC simulation for improving EMC performance of digital I&C systems.
Keywords：EMC simulation；Digital I&C systems50 大亚湾核电站LHP/Q系统控制过程仿真 杜预1，施海宁1，陈耀玲2，丁俊超2 1.苏州热工研究院
2.大亚湾核电运营管理有限公司技术部工程处摘要：深入研究了大亚湾核电站6.6KV应急柴油发电机（LHP/Q）系统的组成、工况和控制逻辑，为其建立了数学仿真模型，并以Visual C++为平台开发软件，实现了该系统逻辑关系和控制过程的仿真，为该系统故障时的维修辅助诊断和正常时的员工教学培训提供了高效便捷的手段。
关键词：大亚湾核电站；应急电源系统；逻辑控制；仿真
Abstract：In order to realize the simulation of logical relationship and control process, the composition, working conditions and control logic of Daya Bay nuclear power plant‘s LHP/Q system is investigated, the mathematic simulate model is built, and then a Visual C++-based simulation software is developed which provide a efficient and convenient means of maintenance and training for the LHP/Q system.
Keywords：Daya Bay nuclear power plant; Emergency power system;Logical control; Simulation51 流体系统模型开发过程及测试要点分析 魏来，陈森 中核集团三门核电有限公司 摘要：三门核电一号模拟机采用AP1000全范围模拟机，根据系统类型和建模工具的不同可以划分为堆芯系统，一回路热工水力系统，流体系统（汽液两相、单相），仪控系统以及电气系统，其中流体系统数量（70个）占到系统总数（85个）的82%。笔者在美国GSE公司岗位培训期间作为模型工程师负责了乏燃料池冷却系统建模。本文以该流体系统的仿真过程为例对模型开发要点进行了分析，同时针对一号模拟机测试即将开始，笔者对模拟机国标、美国模拟机标准、一号模拟机测试大纲中的测试标准、测试范围、测试内容进行了比对，分析、总结了测试要点。
关键词：流体系统 建模；测试52 偏差项电子化管理软件在核电全范围模拟机中的应用 吴帆，郑伟 中广核仿真技术有限公司 摘要：本文论述了自主研发的模拟机偏差项电子化管理软件在核电厂全范围模拟机研发阶段的功能与作用，并结合我国首台自主开发的百万千瓦级压水堆核电全范围模拟机——宁德核电厂一期工程全范围模拟机项目进行了总结。
关键词：偏差项电子化管理软件；核电全范围模拟机；研发；应用
Abstract：Contacting with Ningde Nuclear Power Project Phase I, The paper describes the function and effection of the self-developed Discrepancy Reports software in Full Scope Simulator.
Keywords：Discrepancy Reports software；Nuclear Power Full Scope Simulator；Development Application53 仿真模拟机性能测试 苏学丰 中广核（北京）仿真技术有限公司 摘要：本文就模拟机性能测试几个方面包括人员要求、测试依据与准则、测试结果分析展开论述。最后介绍中广核（北京）仿真技术有限公司（以下简称仿真公司）测试组的优势与未来发展潜力。
关键词：模拟机；性能；质量；测试；准则；分析
Abstract: The performance test of the full scope simulator includes personnel requirements, test basis and standard and the test results analysis. Finally, introduce advantages and future development potential of the test group of CNPSC.
Keywords: Simulator；Performance；Quality；Test；Criteria；Analysis54 培训模拟机数据更新及偏差解决方法的探讨 郑 添，马 骏 上海核工程研究设计院 摘 要：本文主要基于常规核电厂全范围培训模拟机项目的工程经验，提炼出两种培训模拟机数据更新及偏差解决的方法，并通过两种方法的特点比对和理论分析，提出了具体的改进措施。
关键词：核电厂，培训模拟机，现场调试，数据更新，偏差解决
Abstract：This thesis introduces two methods of data updating and discrepancy solution for conventional nuclear plant training simulator, based on experience of Full-Scope Training Simulator Project. Then it proposes an improved method according to comparative theoretical analysis.
Keywords：Nuclear power plant；Training simulator；Site commissioning；Data updating；Discrepancy solution55 核电厂全范围模拟机调试和测试进度安排优化浅谈 王晓星，庄进，吴毅 中广核工程有限公司设备采购与成套中心 摘要: 此文分析了核电模拟机对机组安全运行的重要性以及目前国家对机组投运的相关规定，其制约了模拟机的交付进度；然后又通过深入剖析核电模拟机交付进度要求与参考机组的工程建设实际进度存在―固有矛盾‖，结合核电模拟机的开发流程论证了传统的―集中测试、一步到位‖的开发流程已经满足不了模拟机按期投运的要求；从而详细介绍了核电模拟机流程优化的原则和策略，深入阐述了具体优化的方法。其良好的实践成果可以被后续新建模拟机的开发所借鉴。
关键词： 人因；固有矛盾；流程优化；方法；一步到位；逐步到位
Abstract: This Thesis analyze the importance of Nuclear power station safe operation and relevant national regulation of Unit putting into operation. These factors restrict the delivery schedule of FSS. After that, this thesis also thorough analyze "inherent contradiction" between the delivery schedule of FSS with the actual progress of reference actual Unit. Base on this analysis and the development process of FSS, it prove that the traditional development process of FSS ―Concentration Test, Once for all‖ can‘t meet the requirement of FSS putting into operation at present. This Thesis also introduces that Process optimization principles and strategies of FSS and thorough expound the optimization method. This Good practical achievement can be referred by the follow-up FSS Project.56 核电厂全范围模拟机建造工程的测试过程程序化管理研究 郑伟，胡安平 中广核（北京）仿真技术有限公司 摘要: 本文结合程序化管理方法，研究核电厂全范围模拟机建造工程的测试过程程序化管理的可行性及程序化管理方法，指出将程序化管理方法应用到模拟机建造工程的测试过程中，对于缩短模拟机测试工期、提高模拟机建造质量进而完成整个模拟机建造工程项目的总体目标具有重要推动作用。
关键词：核电厂；全范围模拟机；测试；程序化管理
Abstract: This article researches the feasibility of programmed management method in the nuclear power plant full scope simulator testing and gives some programmed management methods. At the end, this article concludes that the application of programmed management methods in the simulator testing process will play an important role in shortening the simulator test duration, improving the quality of simulator to complete the overall objective of the simulator construction project.
Keywords: Nuclear Power Plant; Full Scope Simulator; Test; Programmed Management57 模拟机测试差异（CR）分析及其用途 王晓星，吴毅，庄进 中广核工程有限公司设备采购与成套中心 摘要：由于核电站模拟机涉及的系统多，而且包括安全级和非安全级等，所以一般都采用多方供应商联合供货的方式。但是在测试期间，如何在海量信息中甄别，跟踪和推动多方产生的重要测试问题，就成为一个难点。迫使我们不得不进行测试差异分析，从众多信息中筛选出我们需要的信息，如阻碍测试的难点问题，问题解决的进展和风险等；依靠多样的问题分析方法让供应商和测试人员更清楚问题所在，从而集中优势资源解决这些重点问题，从根本上保证我们测试的进展顺利。
关键词：测试差异（CR）；差异分析；实时跟踪
Abstract: At present, Nuclear power station involve numerous system and include safety DCS and non-safety DCS, so this way of multi-vendor supply be adopted normally. During our testing, it‘s difficult point how to classify; track and control major testing issues by magnanimity information. So we have to make the variation analysis of FSS Testing. Base on this analysis, we can get our requirement information. For example, Test major issues, the progress and risk of issue solving. Variety of analytical methods can help all test personnel to find out blocking issues of FSS testing. After that, test group can concentrate superior resources to solve these Major issues and ensure our test and project progress.58 浅谈核电站FSS热态零功率下的堆芯测试 龚海洪 CNPEC模拟机组 摘要：阳江核电站采用的是目前成熟的CPR1000技术，所以其全范围模拟机的堆芯模型也日趋成熟，本文主要讨论的是在FSS集成测试阶段期间，在热态零功率条件下，对堆芯所做的物理特性测试时所遇到的问题，以及需要密切关注的一些注意事项。
关键词：压水堆；热态零功率；堆芯物理特性测试
Abstract: As Yang Jiang nuclear plant applies the popular CPR 1000 technology, so the core model for the FSS is good. In this essay, we mainly note that during the FSS integration time what the problem we meet when we do physical test on the core model under the condition of power zero.59 宁德模拟机项目中多测试平台的建设 张潇，林克军 中广核（北京）仿真技术有限公司 摘要：本文描述了宁德全范围模拟机开发过程中多测试平台的构想提出、设计、安装、使用、管理和维护方面的工作，为测试工作及整个项目的顺利进行奠定了基础。
关键词：FSS 多平台建设；测试
Abstract：This article describes the process of developing the concept of multi-platform test proposed design,installation,use,management and maintenance work for the Ningde full scope simulator, it has laid the foundation for the test work and the smooth progress of the project.
Keyword：FSS multi-platform，test60 岭澳二期核电站工程仿真验证平台开发及应用 谢红云，张矾，卢超，徐晓臻，张焕欣 中广核工程设计公司 摘要：岭澳二期核电站采用数字化DCS后，首次在国内开展核电站先进控制室及人机接口的自主设计工作，属于重大技术创新。新型主控室设计需要进行验证和确认（V&V），以保证能够维持电厂安全可靠地运行。利用先进的计算机仿真技术，建设工程仿真验证平台，作为数字化先进控制室技术方案论证和优化的主要工具，为自主设计质量提供了重要保障。
关键词：核电厂；仿真；V&V；DCS
Abstract: The self-design for nuclear power plant advanced MCR and HFI in the LAO II DCS system is first started up in China. In order to make sure the safety and security operation of nuclear power plant, the new design should be verification & Validation (V&V). The engineer V&V platform based on computer simulation technology was built as the main tool of advanced MCR technical project and optimization. It can be an important guarantee for the self-design quality.
Key words: nuclear power plant; simulator; V&V；DCS61 CPR1000项目DCS缺省值在仿真验证平台中的应用 顾海霞，苏朝葵，张焕欣 中广核工程有限公司设计院 摘要：本文针对CPR1000项目核电厂DCS缺省值的相关内容进行简要介绍，重点是通过仿真验证平台对DCS缺省值进行虚拟验证，建立了DCS缺省值验证系统和评价系统。通过缺省值验证系统的结果，改进或设计出更加有效的DCS系统缺省值，从而在CPR项目设计阶段增加核电站的安全性、经济性，提高核电站运行、维护等方面的可靠性。
关键词：缺省值；质量位；DCS； CPR1000仿真验证平台
Abstract: In this paper, it is briefly introduced that nuclear power plant DCS CPR1000 projects related to the contents of the default value, focusing on through simulation platform verifying the default of DCS, and develop DCS default verification and estimating system. By the results of verification system to improve or design more effective DCS system default in the project designing phase, and to increase the safety ,economy and reliability of nuclear power.
Keywords: DCS default value；Quality bit；DCS；CPR1000 simulation and verification platform62 核电 DCS 设计验证平台开发 邓戈燕，刘颖，曲鸣，郑明 中核武汉核电运行技术股份有限公司 摘要：FES (Full Engineering Simulator) 是为核电站分布式控制系统（Distributed ControlSystem，DCS）设计提供工程验证的仿真平台。核电系统主控室、辅助控制室以及远程操作站点提供给操作员的操作界面必须满足便于操作、安全、高效等要求。设计人员依据人因工程要求提出核电站分布式控制系统相关设计方案，验证平台开发人员通过仿真的方式实施设计方案，给设计验证人员提供检验控制室设计是否满足操作员需求的软硬件平台。同时，高效的验证工具也保证了验证平台使用的有效性。验证工作覆盖的范围有现场工艺过程模型正确性、DCS一层控制逻辑与二层显示的设计兼容性，DCS二层操作界面的设计完整性及合理性，DCS二层画面的设计合理性，计算机化信息系统等人机界面相关软件等。
关键词：验证平台；人机界面 验证；分布式控制系统
Abstract：Full Engineering Simulator is a simulate platform of Human Factors Verification and Validation (V&V) for Nuclear Power Systems Distributed Control System (DCS). The Human Machine Interface (HMI) of main control room, auxiliary control room and remote operating site in Nuclear power system must be convenience, safe and effective for operators. Full Engineering Simulator provides a software platform for testing DCS design, and designers can modify the design in accordance with human factors. Meanwhile, some efficient verification tools have been developed to ensure the effectiveness of V&V. The scope of simulation includes nuclear power technical system (Level 0), Instrument and control (I&C) system (Level 1), HMI (Level 2), and the objects of V&V are validate the correctness of three levels, the compatibility between Level 2 and Level 1, integrity andreasonable of Level 2.
Keywords：Full Engineering Simulator； human machine interface； Verification and Validation；
Distributed control system63 基于SmartPlant3D平台的核电站三维设计仿真技术应用研究 张 旭，袁琳,石 琦 中核能源科技有限公司 摘要：本文结合实际核电站工程，以基于SmartPlant3D平台的核电站三维设计仿真技术应用为重点，实现整个核电站生命周期中比重最大的工程设计仿真，从源头上提高设计效率、保证设计质量、指导现场施工，从而控制整个工程的投资成本，同时为核电站后期的运维和退役提供了有效的设计信息依据。
关键词: 三维设计；SmartPlant3D；功能拓展；工程效益；投资成本
Abstract: In this paper, the topic is focus on the 3D Nuclear Plant simulation technology with the SmartPlant3D in actual nuclear project. In order to save the project cost, improve the design efficiency, and guide the construction, we developed the 3D Nuclear Plant simulation Technology, which can control investment cost of the project. Meanwhile, this can provide effective design information for nuclear power plant operation and maintenance.
Key words：Three-dimensional design；SmartPlant3D；Function Development；Project Benefit；Investment costs64 一种乏燃料后处理系统安全工程能力成熟度评估系统 刘志明1 ，阳小华1，刘振海1，万亚平1，白小峰2 1南华大学计算机科学与技术学院2 中国核工业集团四〇四有限公司安防处 摘要：SSE-CMM可用于过程改进、能力评估和提高用户的信任度，是组织和实施安全工程的通用方法，是系统安全工程领域成熟的方法体系。SSE-CMM结合了计算机科学中的CMM模型、管理学中的全面质量管理思想和统计理论，将系统安全工程转换为一个具有良好定义的、成熟的、可测量的先进工程学科。SSE-CMM评估面临领域知识缺乏、数据量大、证据类型多样、过程繁琐、证据与问题匹配复杂等问题。为有效提高评估效率，本文依据本体论、证据理论、语义网、智能信息检索、智能自动匹配等技术和方法，针对乏燃料后处理系统，设计了一种基于领域本体的智能评估软件系统，主要包括领域本体建模和管理、证据自动收集、问题和证据自动匹配、过程评估等四个子系统，技术体系结构分为数据层、本体层、知识层、服务层、表示层五层。目前，该系统已运行于中国动力堆乏燃料后处理中间试验工厂（中试厂）乏燃料接收与存储过程，以后将运用于整个生产过程。
关键词：乏燃料后处理系统；SSE-CMM；本体；证据；评估
Abstract: We can improve process, evaluate capability and promote user's trust degree by SSE-CMM.SSE-CMM is the common method for organize and implement safety engineering, and it is a mature method for system safety engineering. Combining CMM model with total quality management and statistic theory, SSE-CMM makes systems security engineering into a well-defined, mature, measurable, advanced engineering disciplines. Lack of domain knowledge, data is large and the evidence is diversed. The process cumbersome and the complexity of evidence match the issues and problems are the main problems that SSE-CMM assessment field has to be faced. To effectively improve the assessment of efficiency, this paper designed a intelligent assessment software based on domain ontology, and used method such as ontology, evidence theory, semantic web, intelligent information retrieval and intelligent auto-matching techniques and so on. This software includes four subsystems which are domain ontology creation and management system, evidence auto collection system, problem and evidence matching system. The architecture of software is divided into five layers: data layer, ontology layer, knowledge layer, service layer and presentation layer. Currently, the system was to be used (put into use) in spent fuel receiving and storage process of the Chinese power reactor spent fuel reprocessing pilot plant and it will be applied in the entire production process then.
Keywords: Spent Fuel Reprocessing System; SSE-CMM; Ontology; Evidence；Assessment65 核电站模拟机操作员站人机界面软件探讨 章 旋 中广核仿真技术有限公 摘要：从核电站全范围模拟机操作员站的人机界面需求出发，探讨了人机界面软件的功能和性能要求，以及用于模拟机的特殊要求，分析了软件的结构和实现方式。
关键词：核电站；模拟机；操作员站；人机界面软件
Abstract： Based on the requirement of HMI of Simulator for Operator Station in NPP, the function and capability of the HMI software are be discussed that including special requirement for simulator. The structure and technique of the HMI software are be analyzed.
Keywords：Nuclear Power Plant；Simulator；Operator Station；Human Machine Interface Software66 工业组态软件在AP1000工程分析器中的应用 龚湛，林萌，刘鹏飞，杨燕华 上海交通大学核科学与工程学院 摘要：介绍了AP1000工程分析器的结构，然后在已经调试好的AP1000热工模型及控制系统模型的基础上，编制工业组态软件组态程序及友好的人机界面，开发设计工程分析器，并利用该工程分析器进行了稳态及各种瞬态工况测试。研究表明工业组态软件的运用完善了工程分析器的功能，该分析器能较好的模拟各种瞬态工况，分析器的开发给AP1000的培训人员及设计人员提供一定的培训或参考。
关键词：AP1000；工业组态软件；工程分析器；瞬态测试
Abstract: Describes the structure of AP1000 project analyzer, and then bases on AP1000 thermal model and control system models, completes the design of AP1000 project analyzer, through developing industrial configuration software configuration process and friendly man-interface. The project analyzer is used for the steady state and various transient condition tests. Studies have shown that improve the function of AP1000 project analyzer with the using of industrial configuration software, the analyzer is capable of simulating a variety of transient conditions, and the development of the analyzer could provide some training or reference for the AP1000 designer and the training staff.
Key words: AP1000; industrial configuration software; project analyzer; transient condition test67 基于SmartPlant 3D的模型可视化辅助设计 郑海波，张旭，李俊男 中核能源科技有限公司 摘要：SmartPlant 3D（SP3D）是近二十年来出现的先进的工厂设计软件系统。由于核电工程建设领域的特殊性，SP3D自带的元部件库无法满足实际工程设计的需要，由此产生了按照实际图纸定制开发新的元部件的必要性。
传统的SP3D模型开发方法要求元部件模型开发人员具有程序员背景，即使代码编译通过，在没有导入SP3D前是无法验证元部件模型的设计外形是否与图纸一致的，而且不同专业元部件对应的导入文件也需要培训，这就造成了传统的开发方法具有开发周期长、人力成本高的缺点。
为解决上述问题，本文给出了一种基于SP3D的模型可视化辅助设计的方法及系统实现。与传统方法相比，具有可见即可得的设计环境、人员要求较低、代码自动生成、各专业导入文件自动生成等优点，提高了开发效率，节省了开发成本。
关键词：SmartPlant 3D；可视化辅助设计；3D模型；元器件库
Abstract：SmartPlant 3D(SP3D) was one of the most advanced plant design system. Because of the nature of nuclear power construction field, SP3D‘s own symbol library cannot meet the needs of engineering design. So, requirement of development of new symbols appears.
The traditional method of SP3D model development requires the designer have background of programming. And even if the code compiled success, we cannot verify whether the symbols have the same shape with the drawings before bulkload into SP3D. And different task‘s data files also need to study. As a result, traditional method has many shortcomings such as long development cycle and high labor costs.
To solve these problems, this paper presents a SP3D .net API based visualized aided design system. Compared with traditional method, we have a environment which what you see is what you get, and have no programming requirement to designer, and have the ability to automatic generate corresponding code and data files. Our method rapidly increases the efficiency meanwhile development cost decreased.68 基于LT-Spice仿真平台的电源冗余控制电路设计 陈博，金成日，杨凯生，李熊 北京广利核系统工程有限公司 摘要：本文介绍了利用LT-Spice软件对模拟电源电路进行仿真分析的方法。该方法先建立器件模型，绘制电路图，再利用LT-Spice进行瞬态仿真波形分析。优化后的电路已成功应用于数字化仪控系统电子电路中，实践证明，该仿真方法对数字化仪控系统硬件电路设计具有指导作用。
关键词：LT-Spice 仿真；LTC4352；DCS
Abstract: In this paper, a new simulation method using LT-Spice software to simulate power analog circuits is presented. The method is to create model, draw logic schematic and analyze transient wave. The circuit is successfully used in Nuclear Digital Control System (DCS). Through practice, the simulation method is helpful to circuit design in Digital Control System69 OPC通讯技术在电厂仿真项目中的应用 印勇，刘仪 中广核（北京）仿真技术有限公司 摘要：本文介绍了一种采用OPC通讯技术用于让OVATION 虚拟DPU系统与ASCA仿真平台进行通讯，从而实现数据的实时交换。满足了模拟机的实时要求。
关键词：OPC通讯技术；模拟机
Abstract：This paper introduces an OPC communication technology used to make the DPU system of OVATION virtual and ASCA simulation platform for communication, enabling real-time data exchange. Meet the requirements of real-time simulator. Keywords：OPC communication technology；Simulator70 RockWell I/O系统在核电站仿真机中的应用 张汉泉 中广核（北京）仿真技术有限公司 摘要：本文从网络结构、系统组态、数据通讯等各方面阐述了Rockwell公司的ControlLogix系列产品在核电仿真机I/O接口系统中的应用。
关键字：仿真机、I/O接口系统、RockWell、ControlLogix、ControlNet、BTD71 一种基于文本模板技术的IEC61131-3控制算法转换机制 钟俊，章旋，魏会明，张学斌 中广核（北京）仿真技术有限公司 摘要：设计了一种基于文本模板技术的IEC61131-3标准控制算法转换机制；重点研究了ST语言编写的控制算法转换成C++算法的过程；最后在3KeyMaster平台上进行了测试验证。
关键字：IEC61131-3；ANTLR；文本模板；ST语言；3KeyMaster
Abstract：This article designed a conversion mechanism for IEC61131-3 control algorithm based on StringTemplate technology. The paper then focused on the process that translating the control algorithm written in ST language into C++ language. Finally, 3KeyMaster is used to test and validate the mechanism.
Keywords：IEC61131-3；ANTLR；StringTemplate；ST Language；3KeyMaster72 在核电站模拟机上应用基于web服务的分布式仿真框架 张光昱 中广核（北京）真技术有限公司 摘要：随着核电站控制系统的快速发展以及DCS的加入，系统结构和功能都愈加复杂，因此在规定时间内，如何快速，大批量的生产模拟机系统成为一个重要课题。本文就建立基于web服务的仿真动态框架来解决这个课题进行尝试性探讨。
关键词：分布式仿真；web；SOA；核电站模拟机；系统架构
Abstract：With the developing of nuclear station control system, especially using DCS,the struction of system becomes more and more complicated.we need to find a way to produce the simulator of main control room which can follow this developing.This paper shows a research on a struction of SOA based on web which try to give a solution.