基于虚拟现实技术的“华龙一号”主控制室模拟机系统

主控制室是维持核电厂安全和正常运行的重要场所,人的因素是主控制室设计和电厂运行当中的重要环节,因此核电厂通常使用主控制室模拟机对主控制室的人因工程性能进行验证并对操纵员进行训练。传统的模拟机技术一般需要构建1∶1的实际主控制室模型。对于设计者,在主控制室模拟机房内实施设计修改并评估效果较为困难,同时不同型号的主控制室需要独立的模拟机房间,随着工程项目的更迭存在所占空间大、复用率低的问题。对于运营单位的训练任务,一套占地约300m2的主控制室模拟机同时只能供一组操纵员进行训练,对于机组数量较多的厂址,需要配备一定规模的模拟机中心才能满足训练需求。基于以上情况,"华龙一号"的设计过程中提出了一套基于虚拟现实技术的主控制室模拟机方案,使用虚拟现实设备和其他人机接口在最小化的空间内构建主控制室的实际环境,相对于传统模拟机的方案,基于虚拟现实技术的模拟机成本低、灵活性强,在工程设计初期弥补传统模拟机系统的空缺,同时为操纵员训练提供多样化的手段。     

秦山核电厂主控制室盘台更新设计研究与实践

秦山核电厂针对主控制室及应急控制室存在的问题,基于核安全相关法规及核电厂设计标准提出了盘台结构及设备改进总体要求和设计原则,明确了盘台及设备设计改进的具体方案,分析论证了设计改进的合规性.设计于2018年实施并取得了良好效果,为其他核电厂后续进行主控制室相关改造及新项目设计提供了实践经验.     

核电厂先进主控制室功能分析和功能分配

根据先进压水堆研究关键课题－先进主控制室的设计研究,阐述了核电厂主控制室设计中进行功能分析与功能分配的基本要求,重点论述了功能分析与分配的内容、作用、重要性与必要性。探讨了在核电厂先进主控制室的设计中贯彻执行这些要求的措施及进行设计验证的方法。     

压水堆核电站先进控制室布置设计

主控制室设计首先应保证核电站的安全运行,尽量减轻操作人员的运行压力.设计中应充分考虑软硬件平台的多样性,数字化人-机接口和后备盘的多样性,主控制室和应急控制室场所的多样性.由于不同的供货商所采用的法规、标准不完全相同,控制室的布置设计差异较大,在主控制室系统的设计和采购时,还需要考虑设备所在国的法规和标准,并满足我国法规和标准的要求.     

秦山核电厂主控制室更新技术研究与策划

基于运行许可延续（OLE）的需求，为确保主控制室与应急控制室（简称主控室和应控室）的设计及设备符合国家核安全相关法规及标准要求，通过对秦山核电厂主控室及应控室的盘台现状、人机接口进行调查和分析，对盘台结构、设备改进及人机接口再设计进行了研究，提出了主控室和应控室整体更新的解决思路并开展了可行性论证，策划了总体设计更新方案、验证流程和实施管控方法。工程实践及运行业绩表明本研究方法是有效的，可为核电机组OLE研究提供指导。     

核电厂先进的主控制室相关技术研究

先进的主控制室系统是以网络技术和计算机技术为基础的分布式计算机监控系统.本文阐述了核电厂主控制室设计中人-机接口的重要性,描述了主控制室实验开发平台的配置及其功能分区与分配,并介绍了该平台完成的功能及先进控制室的特点.     

核电厂控制室控制功能切换方案研究

核电厂为运行人员提供了主控制室（MCR）作为电厂集中监控中心,并提供了与MCR实体隔离和电气隔离的远程停堆站（RSS）作为辅助控制室,以在MCR不可用时投入使用,对电厂实施监控,并将电厂带入停堆状态和导出余热。根据核安全法规、导则及标准要求,来自MCR和来自RSS的电厂控制功能须相互闭锁,不能同时执行。本文通过比较分析,研究CPR1000、EPR及AP1000堆型核电厂控制室操作模式切换方案的特点与不足,在详细研究的基础上给出控制室切换功能设计的几个基本原则,供新的核电厂控制室功能切换方案设计时参考,以设计出更为实用、简洁、安全、便利的方案。     

核电厂先进主控制室的发展概况与自主设计研究的内容和目标

描述了当今世界上核电厂先进主控制室的开发与工程应用的概况如N4、系统80+、ABWR与APWR等,简述了各自的技术路线、达到的技术水平.论述和分析了在将采用数字化控制、保护、显示和操作设备后的我国新一代核电厂的设计中,进行先进主控制室的自主设计研究的技术背景与技术需求、技术路线、设计研究的内容与目标.     

关于控制室可居留性若干问题的讨论

从控制室包络(CRE)边界的完整性、控制室可居留性分析所用源项以及影响控制室剂量后果的其他因素等几个方面,结合美国及我国在控制室可居留性方面的管理规定及我国核设施在控制室可居留性方面的研究现状进行讨论,建议我国核设施应考虑通过进行CRE完整性测试来获取CRE渗入量的数据,为控制室可居留性分析提供输入参数,此外,在控制室人员后果计算中应考虑不同事故及可能的不同路径作系统的分析。     

秦山CANDU 6机组主控制室改进

介绍了秦山ＣＡＮＤＵ６机组因考虑到ＣＡＮＤＵ９设计的新技术,对主控制室所作的设计改进。主要是大屏幕显示器和配套的电站显示系统,优化的ＣＲＴ报警系统和美学设计改进。     

核电厂主控室取风口监测仪表设置研究

核电厂主控室取风口监测仪表是为了监测取风口处的放射性核素浓度或环境剂量率,并与通风系统联动,进行取风口的切换。在事故后根据正常取风口处的剂量率监测仪表的监测数据可从正常通风系统切换至带过滤功能的应急通风系统,根据两个应急取风口处的β活度监测仪表的监测数据选择污染物浓度较低的应急取风口。因此取风口处监测仪表的设置对事故后保证主控室区域的可居留性至关重要。本文针对主控室通风系统正常取风口和应急取风口的监测仪表的设置进行研究,利用某厂址一整年气象数据,根据华龙一号机型典型事故源项、通风系统设计性能及主控室建筑结构特征对事故情况下从正常通风系统切换到应急通风系统的报警阈值进行分析计算,并结合监测仪表的响应特征,针对大气释放阀释放、安全壳释放和高架释放3种释放类型,分析了相应事故工况下主控室双取风口在不同的切换间隔条件下主控室工作人员所受剂量,最后给出推荐的主控室双取风口最短切换时间间隔。本文对取风口监测仪表设置方法的探索和研究为未来同类主控室通风系统监测的设计和优化提供了参考。     

Development of a standard communication protocol for an emergency situation management in nuclear power plants

Correct communication between main control room (MCR) operators is an important factor in the management of emergency situations in nuclear power plants (NPPs). For this reason, a standard communication protocol for the management of emergency situations in NPPs has been developed, with the basic direction of enhancing the safety of NPPs and the standardization of communication protocols. To validate the newly developed standard communication protocol, validation experiments with 10 licensed NPP MCR operator teams was performed. From the validation experiments, it was found that the use of the standard communication protocol required more time, but it can contribute to the enhancement of the safety of NPPs by an operators’ better grasp of the safety-related parameters and a more efficient and clearer communication between NPP operators, while imposing little additional workloads on the NPP MCR operators. The standard communication protocol is expected to be used to train existing NPP MCR operators without much aversion, as well as new operators.     

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。     

事故下CAP1000核电厂主控室剂量特征研究

核电厂事故期间,为使主控室工作人员能够坚守岗位缓解事故后果,必须保证主控室的可居留性。放射性水平作为主控室可居留性的重要考虑因素,主控室人员接受的剂量必须满足相关标准导则的要求。本文以弹棒事故为参考工况,对事故情况下主控室的剂量特征进行了分析,给出了不同通风模式下的剂量结果,不同释放途径和不同核素组对剂量的贡献,以及剂量随时间的变化情况。针对CAP1000主控室非能动应急可居留系统设计,对该系统关键参数对剂量影响的敏感性进行了分析。研究结果为进一步深化事故后主控室剂量分析和可居留性优化改进提供了支持。     

Development and validation of a heuristic model for evaluation of the team performance of operators in nuclear power plants

The global concerns about safety in the digital technology of the main control room (MCR) are growing as domestic and foreign nuclear power plants are developed with computerized control facilities and human–system interfaces. In a narrow space, the digital technology contributes to a control room environment, which can facilitate the acquisition of all the information needed for operation. Thus, although an individual performance of the advanced MCR can be further improved; there is a limit in expecting an improvement in team performance. The team performance depends on organic coherence as a whole team rather than on the knowledge and skill of an individual operator. Moreover, a good team performance improves communication between and within teams in an efficient manner, and then it can be conducive to addressing unsafe conditions. Respecting this, it is important and necessary to develop methodological technology for the evaluation of operators’ teamwork or collaboration, thus enhancing operational performance in nuclear power plant at the MCR.     

Development of task analysis method for operator tasks in main control room of an advanced nuclear power plant

Task analysis methods provide an insight for quantitative and qualitative predictions of how people will use a proposed system, though the different versions have different emphases. Most of the methods can attest to the coverage of the functionality of a system and all provide estimates of task performance time. However, most of the tasks that operators deal with in a digital work environment in the main control room of an advanced nuclear power plant require high mental activity. Such mental tasks overlap and must be dealt with at the same time; most of them can be assumed to be highly parallel in nature. Therefore, the primary aim to be addressed in this paper was to develop a method that adopts CPM-GOMS (cognitive perceptual motor-goals operators methods selection rules) as the basic pattern of mental task analysis for the advanced main control room. A within-subjects experiment design was used to examine the validity of the modified CPM-GOMS. Thirty participants participated in two task types, which included high- and low-compatibility types. The results indicated that the performance was significantly higher on the high-compatibility task type than on the low-compatibility task type; that is, the modified CPM-GOMS could distinguish the difference between high- and low-compatibility mental tasks.     

Investigating the effect of task complexities on the response time of human operators to perform the emergency tasks of nuclear power plants

For many decades, since the reliable performance of human operators is decisive for securing the safety of large process control systems, proceduralized tasks have been widely used to enhance their performance. For this reason, TACOM measure has been developed to quantify the complexity of proceduralized tasks to be conducted by operating personnel working in nuclear power plants (NPPs), because it is strongly expected that complicated tasks could directly result in the degradation of human performance. This expectation seems to be supported by comparing two kinds of human performance data (response time data and subjective workload scores) obtained from the simulated emergency situations of domestic NPPs with the associated TACOM scores. In addition, the results of previous studies make it possible to assume that the performance of human operators would be comparable if they have to accomplish a series of proceduralized tasks having similar levels of task complexities. In this study, in order to scrutinize the appropriateness of this assumption, response time data originated from domestic as well as overseas NPPs were compared with the associated TACOM scores. As a result, it was observed that TACOM scores are important to explain the changes of response time data collected from both the domestic and the overseas NPPs. Therefore, although additional studies are indispensable, this result is meant to show that the performance of human operators would be largely affected by the levels of task complexities, which can be properly quantified by TACOM measure.     

核电厂数字化SOP对人因失误的影响

主控室中数字化状态导向规程SOP(State-oriented Procedure)的应用使操纵员执行事故处理的逻辑和信息显示方式都发生了重大变化。本文介绍了SOP规程的原理,描述了数字化主控室中操纵员执行SOP处理电厂事故的流程。以核电厂主控室现场调研、行为观察、模拟机实验和操纵员访谈为依据,发现数字化SOP在操作控制、信息显示、班组合作等方面带来了大量可能导致人因失误的因素,以及可能出现的新的人误模式,可期为SOP规程的优化提供支持。     

基于二元重要度的设备分级技术

现有的概率论设备分级方法在重要度方法选取、计算方法和分级限值制定等方面存在不足.本文把二元重要度决策法与叠加性转移模型相结合.以基于后果的风险评判为标准,为上述问题的处理提供了合理的理论依据.在秦山二期扩建核电站概率安全分析模型的基础上,验证了二元重要度分级方法的正确性.     

核电厂数字化主控室操纵员行为形成因子评价模型

由于人因可靠性分析(HRA)方法中用于量化基本人因失误概率(HEP)的行为形成因子（PSF）数目众多,且一般是通过专家评判,从而带有主观性、模糊性和不确定性。本文提出一种利用相关系数矩阵、图的距离分类和主成分分析法相结合的方法构建核电厂数字化主控室操纵员PSF的评价模型,其目的是识别不同类型的人因事件中主要影响人因绩效的PSF,以供决策减少人因失误。对某核电厂的179起人因事件报告进行实验,结果表明该评价模型能对核电厂数字化主控室操纵员的PSF进行有效评价。