Lecture Notes in Electrical Engineering 595

Yang Xu · Yongbin Sun · Yanyang Liu · Yanjun Wang · Pengfei Gu · Zheming Liu   Editors

Nuclear Power Plants: Innovative Technologies for Instrumentation and Control SystemsThe Fourth International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant (ISNPP)

Lecture Notes in Electrical Engineering

Volume 595

Series Editors

Leopoldo Angrisani, Department of Electrical and Information Technologies Engineering, University of NapoliFederico II, Naples, ItalyMarco Arteaga, Departament de Control y Robótica, Universidad Nacional Autónoma de México, Coyoacán,MexicoBijaya Ketan Panigrahi, Electrical Engineering, Indian Institute of Technology Delhi, New Delhi, Delhi, IndiaSamarjit Chakraborty, Fakultät für Elektrotechnik und Informationstechnik, TU München, Munich, GermanyJiming Chen, Zhejiang University, Hangzhou, Zhejiang, ChinaShanben Chen, Materials Science and Engineering, Shanghai Jiao Tong University, Shanghai, ChinaTan Kay Chen, Department of Electrical and Computer Engineering, National University of Singapore,Singapore, SingaporeRüdiger Dillmann, Humanoids and Intelligent Systems Lab, Karlsruhe Institute for Technology, Karlsruhe,Baden-Württemberg, GermanyHaibin Duan, Beijing University of Aeronautics and Astronautics, Beijing, ChinaGianluigi Ferrari, Università di Parma, Parma, ItalyManuel Ferre, Centre for Automation and Robotics CAR (UPM-CSIC), Universidad Politécnica de Madrid,Madrid, SpainSandra Hirche, Department of Electrical Engineering and Information Science, Technische UniversitätMünchen, Munich, GermanyFaryar Jabbari, Department of Mechanical and Aerospace Engineering, University of California, Irvine, CA,USALimin Jia, State Key Laboratory of Rail Traffic Control and Safety, Beijing Jiaotong University, Beijing, ChinaJanusz Kacprzyk, Systems Research Institute, Polish Academy of Sciences, Warsaw, PolandAlaa Khamis, German University in Egypt El Tagamoa El Khames, New Cairo City, EgyptTorsten Kroeger, Stanford University, Stanford, CA, USAQilian Liang, Department of Electrical Engineering, University of Texas at Arlington, Arlington, TX, USAFerran Martin, Departament d’Enginyeria Electrònica, Universitat Autònoma de Barcelona, Bellaterra,Barcelona, SpainTan Cher Ming, College of Engineering, Nanyang Technological University, Singapore, SingaporeWolfgang Minker, Institute of Information Technology, University of Ulm, Ulm, GermanyPradeep Misra, Department of Electrical Engineering, Wright State University, Dayton, OH, USASebastian Möller, Quality and Usability Lab, TU Berlin, Berlin, GermanySubhas Mukhopadhyay, School of Engineering & Advanced Technology, Massey University,Palmerston North, Manawatu-Wanganui, New ZealandCun-Zheng Ning, Electrical Engineering, Arizona State University, Tempe, AZ, USAToyoaki Nishida, Graduate School of Informatics, Kyoto University, Kyoto, JapanFederica Pascucci, Dipartimento di Ingegneria, Università degli Studi “Roma Tre”, Rome, ItalyYong Qin, State Key Laboratory of Rail Traffic Control and Safety, Beijing Jiaotong University, Beijing, ChinaGan Woon Seng, School of Electrical & Electronic Engineering, Nanyang Technological University,Singapore, SingaporeJoachim Speidel, Institute of Telecommunications, Universität Stuttgart, Stuttgart, Baden-Württemberg,GermanyGermano Veiga, Campus da FEUP, INESC Porto, Porto, PortugalHaitao Wu, Academy of Opto-electronics, Chinese Academy of Sciences, Beijing, ChinaJunjie James Zhang, Charlotte, NC, USA

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Yang Xu • Yongbin Sun •

Yanyang Liu • Yanjun Wang •

Pengfei Gu • Zheming LiuEditors

Nuclear Power Plants:Innovative Technologiesfor Instrumentationand Control SystemsThe Fourth International Symposiumon Software Reliability, Industrial Safety,Cyber Security and Physical Protectionof Nuclear Power Plant (ISNPP)

123

EditorsYang XuDepartment of Engineering PhysicsTsinghua UniversityBeijing, China

Yongbin SunChina Techenergy Co., Ltd.Beijing, China

Yanyang LiuNuclear Power Institute of ChinaChengdu, Sichuan, China

Yanjun WangChina Nuclear Power Engineering Co., Ltd.Beijing, China

Pengfei GuChina Nuclear Power Design Co., Ltd.Shenzhen, Guangdong, China

Zheming LiuProduct Information Committee of ChinaInstrument and Control SocietyBeijing, China

ISSN 1876-1100 ISSN 1876-1119 (electronic)Lecture Notes in Electrical EngineeringISBN 978-981-15-1875-1 ISBN 978-981-15-1876-8 (eBook)https://doi.org/10.1007/978-981-15-1876-8

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Preface

In recently years, along with the development of domestic research and interna-tional communications, more digital instrumentation and control (I&C) technolo-gies are used in China’s nuclear power plants, such as the microprocessor-basedsafety I&C system named FirmSys developed by China General Nuclear PowerCorporation, and the safety DCS named NASPIC developed by China NationalNuclear Corporation, etc. In order to solve problems in actual productions andapplications, and to provide a platform for technical discussion, the 4thInternational Symposium on Software Reliability, Industrial Safety, Cyber Securityand Physical Protection of Nuclear Power Plant (ISNPP) which was focused onsoftware and hardware verification and validation and licensing, intelligent main-tenance management and digital update, advanced main control room and HFE,cybersecurity and other advanced technical issue concerned of nuclear powerindustry, was convened by relevant organizations and governmental divisions.

Since 2016, this symposium has become an effective technical forum for nuclearpower utilities, regulators, engineering company, contractors, research institutions,and equipment manufacturers annually. The 4th ISNPP was successfully held inGuiyang, China, from August 21 to 23, 2019. More than 100 experts, researchers,and senior engineers from 34 organizations, including National Nuclear SafetyAuthority, Tsinghua University, the Ministry of Ecological Environment, ChinaTechenergy Co., LTD, State Key Laboratory of Nuclear Power Safety MonitoringTechnology and Equipment, China Nuclear Power Engineering Company Ltd., etc.,as well as institutions and companies from the aerospace industry. The symposiumserved as a platform for exchanging ideas on every aspect of nuclear power plants’instrumentation and control system, and also promoted the military-civilian inte-gration in China.

More than 100 conference papers were submitted for the symposium, coveringtopics including digital instrumentation and control technology, electromagneticcompatibility, main control room and human–machine interface design, softwareverification and validation, etc. After anonymous peer review and selection by theexperts, 56 outstanding papers were finally accepted to the proceedings published inLecture Notes in Electrical Engineering by Springer. During the conference, these

v

authors shared with the audience their latest and most important research progress.In fact, many topics discussed at the symposium provided important reference andstrong support for the related works of nuclear power plant. We believe these paperscould also benefit the entire nuclear instrumentation and control system industry.

On the occasion of the publication of these papers, we would like to thank theorganizers of the symposium for providing a good platform for the majority ofnuclear power practitioners. We are also very grateful to the experts who providedsupport and guidance during the reviewing process. Finally, we would like to thankall the authors, and without whose efforts and studies, this volume would neverhave been published successfully.

Yongbin Sun

vi Preface

Organization

Hosts

Instrumentation Editorial CenterProduct Information Committee of China Instrument & Control Society (CIS-PIC)Nuclear Instrument and Control Technical Division of China Instrument & ControlSociety (CIS-NICT)Professional Committee of Nuclear Facility Cyber Security, Nuclear Safety Branch,Chinese Nuclear Society (CNS)Beijing BOGONGXINGYE Engineering Consulting Co., Ltd.

Organizers

China Nuclear Power Engineering Co., Ltd. (State Key Laboratory of NuclearPower Safety Monitoring Technology and Equipment) (CNPEC)Gui Zhou Aerospace Electrical Appliances Co., Ltd.

Co-organizers

China Techenergy Co., Ltd. (CTEC)Beijing ZHIZAOSHIDAI Exhibition Co., Ltd.China Nuclear Control Systems Engineering Co., Ltd. (CNCS)Hualong Pressurized Water Reactor Technology Corporation, Ltd. (HPR)

EditorsYang Xu Department of Engineering Physics, Tsinghua

University, Beijing, ChinaYongbin Sun China Techenergy Co., Ltd., Beijing, ChinaYanyang Liu Nuclear Power Institute of China, Chengdu,

Sichuan, ChinaYanjun Wang China Nuclear Power Engineering Co., Ltd.,

Beijing, China

vii

Pengfei Gu China Nuclear Power Design Co., Ltd.,Shenzhen, Guangdong, China

Zheming Liu Product Information Committee of ChinaInstrument and Control Society, Beijing,China

Secretary of Organizing CommitteeXiaolian Wang Product Information Committee of China

Instrument & Control Society

Director of Executive CommitteeYuzhou Yu Product Information Committee of China

Instrument & Control Society

viii Organization

Contents

Analysis and Countermeasures of Inconsistency for AcousticDesign and Lighting Design Regulations and Standards in MainControl Room of Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . 1Zhang Gang, Zhao Jinbo, Qi Kai, Cheng Bo, Mei Shibo, and Wang Yan

Application of Mixed Reality Based on Hololens in NuclearPower Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9Yi Zhang, Dan Li, Hao Wang, and Zheng-Hui Yang

Visualization of Geologic Engineering Data Based on NuclearPower Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21Hui Chang

Research on Defense-in-Depth Zone of Low-Altitude SecurityArea in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30Lin Ye, Jie Zhang, and Guang Meng

Research on Axial Power Deviation Safety Early WarningTechnology Based on Online Simulation . . . . . . . . . . . . . . . . . . . . . . . . 38Hong-Yun Xie, Ke Tan, Wei-Jun Huang, Chao Zhang, and Zhen-Yu Shen

Integrated Digital Control Platform for Flywheel Systemswith Active Magnetic Bearings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46Kai Zhang, Yang Xu, and Xing-Jian Dai

Off-Line Performance Calculating Software of the Secondary LoopThermal System in AP1000 Nuclear Power Plant . . . . . . . . . . . . . . . . . 58Zhi-Gang Wu and Wen Chen

Monitoring and Analyzing of Wall Temperature Fluctuationsfor Thermal Fatigue in Elbow Pipe . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69Jun Ling, Hao Fu, Hong-Tao Liu, and Jing-Qi Yuan

ix

Discussions on Information Security Test Strategy for DigitalIndustrial Control System in Nuclear Power Plant . . . . . . . . . . . . . . . . 83Wang Xi, Peng-Fei Gu, and Wei Liu

Study and Implementation on General Operating Procedureof CPR1000 Main Control Room in China . . . . . . . . . . . . . . . . . . . . . . 90Ji Shi, Qing-Wu Huang, Chuang-Bin Zhou, Liang-Jun Xu, and Hui Jiang

Inductive Displacement Sensors Based on the IntegratedDemodulation Chip . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101Ya-Ting Liu, Kai Zhang, and Yang Xu

The Development of TMSR-SF0 Simulation Protection System . . . . . . . 112Guo-Qing Huang, Jie Hou, Ye Liu, Wei Lai, and Bing-Ying Li

Assessment of Operating Safety State of Nuclear Power PlantBased on Improved CAE Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 120Chao Lu, Jia-Lin Ping, Wei-Jun Huang, Ke Tan, and Hong-Yun Xie

Analysis and Solution of Design Difficulties of HMI with ScaleIncrease in Limited Space . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 129Bo Cheng, Ting Mao, Shi-Bo Mei, Xue-Gang Zhang, Yi-Qian Wu,and Zhen-Hua Luan

Application Analysis of Wireless Sensor Networks in NuclearPower Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 135Zhiguang Deng, Qian Wu, Xin Lv, Biwei Zhu, Sijie Xu,and Xuemei Wang

Development and Application of Intelligent Platformfor Collaborative Electrical Design of Nuclear Power . . . . . . . . . . . . . . 149Chao Guo, Yu Zhang, Xin-Wei Xu, Jia-Kun Hu, and Xiao-Fen He

Research on Stewardship-Intensive Digital Procedure System . . . . . . . . 162Hao Qin

Study and Optimization of Load Fluctuation of the TurbineGenerator After Connected to the Grid in Nuclear Power Plant . . . . . . 169Xiao-Lei Zhan, Yan Liu, and Gang Yin

Study for Design and Application of Procedure-Based Automationin Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 176Xue-Gang Zhang, Fang-Fang Gao, Yan-Tong Luo, and Zhi-Yao Liu

Research on KDA System Reliability Model Based on TotalProbability Formula . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 185Ying-Jie Lin, Ze-Yu Xie, and Jie Lin

x Contents

The Research and Application of Test Method for 1E I&C SystemPlatform’s Change . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 194Hu-Jun Jia, Yao Wu, Xiao-Sheng Dong, Min Qi, Xiu-Hong Lv,and Hong-Yan Chen

Research and Application of a User Interface Automatic TestingMethod Based on Data Driven . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 202Tai-Xin Huang, Jian-Wei Ji, Yun-Xu Shou, and Yan Kong

Research on a Certainty Data Link Layer Protocol for theCommunication Network in Nuclear Safety DCS . . . . . . . . . . . . . . . . . . 212Le Li, Chun-Lei Zhang, Kang Cheng, Xing-Xing Sun, and Wen-Yu Yang

A Design of FPGA-Based Self-healing System for CommunicationNetworks in Nuclear Safety DCS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 226Chun-Lei Zhang, Le Li, Kang Cheng, Wen-Yu Yang, and Xing-Xing Sun

A Formal Method for Verifying the Ability of a Protocol to ResistReplay Attacks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 238Ru-Mei Shi, Yun-Bo Zhang, Ya-Dong Zhang, Qiao-Rui Du,Xiao-Bo Zhou, and Xian-Zhu Xu

Design and Analysis of Safety DCS Cabinet for Small MarineReactor Based on the FirmSys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248Zhao-Feng Liu, Zhi-Rui Jiang, Xin Zuo, Wei Chen, and Zhao-Long Li

The Design of Safety Control Display Device of Small ModularOffshore Floating Reactor Protection System Based on FirmSys . . . . . . 258Chun-Lei Zhang, Yu-Nan Fan, Xin Zuo, Ji-Kun Wang, and Yi-Qin Xie

Research on Maintenance Network Design Based on Nuclear PowerStation Safety DCS System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 268Chun-Lei Zhang, Da-Peng Liu, Li Peng, Bao-Hua Ren, and Song Liu

Research and Application of RPN Detector PositioningTechnologies in Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . 281Tian-You Li, Rui Zhang, Ya-Jie Tian, Hua-Qing Peng, Jun Tian, Li Zeng,and Jing Shang

A Safety Level DCS Symbol Execution Test Optimization Method . . . . 294Yan-Jun Dai, Zhi-Qiang Wu, Jie Liu, Zhi Chen, An-Hong Xiao,and Hui Zeng

Application Research of Fault Diagnosis in Conventional Islandof Nuclear Power Plant Based on Support Vector Machine . . . . . . . . . . 304Heng Li, Nian-Wu Lan, and Xin-nian Huang

Software Verification and Validation of Digital NuclearInstrumentation System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 313Mi Zhang, Ju-Zhi Wang, Wei-Jie Huang, and Bing-Chen Huang

Contents xi

Research on the Human Factors Integration in Some ThirdGeneration NPP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 322Zhong-Ping Yin, Yan-Zi Liu, Xue-Gang Zhang, Jian-Bo Zhang,and Xiao-Mei Xu

Development and Application of Closed-Loop Control PerformanceEvaluation System for Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . 335Zhen-Hua Luan, Zong-Wei Yang, Peng Liu, and Jun Liang

Research on Typical Fault Diagnosis of Nuclear Power Plant Basedon Weighted Logical Inference Arithmetic . . . . . . . . . . . . . . . . . . . . . . . 345Yi-Peng Fan, Hong-Yun Xie, and Chao Lu

Information Security Risk Analysis and Countermeasuresof Digital Instrumentation Control System in NPP . . . . . . . . . . . . . . . . . 356Jian-Zhong Tang, Zi-Yin Liu, Hui-Hui Liang, Peng-Fei Gu,and Wei-Jun Huang

The Research and Development of Digital GeneralOperating Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 367Chuang-Bin Zhou, Qing-Wu Huang, Ji Shi, Wei-Hong Cui, Xian-Min Li,Wen-Bin Liu, Yi-Xiong Luo, and Shao-Shuai Qiu

Research on Hybrid Communication System for Nuclear PowerPlants Safety-DCS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 379Zhi-Qiang Chen, Qi Chen, Min-Jie Lei, and Yan-Qun Wu

Analysis of Analog Circuit Error in Reactor Control System . . . . . . . . . 387Qi-Chang Huang, Shun Wang, Xu-Feng Tian, and Zhi-Qiang Wu

Reliability Analysis of Safety Class Analog Output Module Basedon FFTA in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 398Xu-Feng Tian, Cheng Yang, Qi-Chang Huang, and Xu Zhang

Research on Instrument Channel Uncertainty of NuclearPower Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 406Shun Wang, Qi-Chang Huang, Zhi-Qiang Wu, and Ming-Xing Liu

Research and Analysis on 1E Distributed Control System PriorityLogic Module . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 415Zong-Hao Yang, Quan Ma, Ming-Ming Liu, Zi-Peng Zhang,and Kai Wang

Design and Optimization of Communication in Nuclear SafetyClass Emulation System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 430Xu Zhang, Quan Ma, Qi Chen, Kai Wang, Hao Peng, and Guo-Hai Liu

Reliability Allocation Based on Importance Measures . . . . . . . . . . . . . . 441Ming Xu, Duo Li, Shu-Qiao Zhou, and Xiao-Jin Huang

xii Contents

Discussion on Traceability Analysis Method of Safety Softwarein Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 455Peng-Fei Gu, Ya-Nan He, Jian-Zhong Tang, and Wang-Ping Ye

The Application of LSTM Model to the Prediction of AbnormalCondition in Nuclear Power Plants . . . . . . . . . . . . . . . . . . . . . . . . . . . . 463Jing-Ke She, Shi-Yu Xue, Pei-Wei Sun, and Hua-Song Cao

Development and Application of Undisturbed Online Downloadsin the FirmSys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 477Gui-Lian Shi, Bao-Hua Ren, Zhi-Hui Zhang, Xing-Xing Sun, and Le Li

The Study on Automatic Control of Pressure and Temperaturefor the Pressure Water Reactor Nuclear Power Plant . . . . . . . . . . . . . . 492Jia-Lin Ping, Hong-Yun Xie, Chao Lu, Lin Tian, and Chun-Bing Wang

A Hierarchical Task Analysis Approach for Static HumanFactors Engineering Verification and Validationof Human-System Interface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 502Xin-Yu Dai, Ming Jia, Ting Mao, Ming Yang, Jun Yang, Yu-Xin Zhang,and Hong-Xing Lu

Research on Static Testing Technology of Nuclear Safety-CriticalSoftware Based on FPGA Technology . . . . . . . . . . . . . . . . . . . . . . . . . . 516Wei Xiong, Tao Bai, Peng-Fei Gu, Hui-Hui Liang, and Jian-Zhong Tang

Features Extraction Based on Deep Analysis of Network Packetsin Industrial Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 524Wen Si, Jiang-Hai Li, and Xiao-Jin Huang

An Optimum Solutions for Venturi Used for Main FeedwaterFlowrate Measurement in Nuclear Power Plant . . . . . . . . . . . . . . . . . . . 530Zong-Jian Shangguan, Hua-Tong Wei, and Lin Guo

Research and Application of Software Reliability Analysis Methodfor Safety I&C System in NPPs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 541Sheng-Chao Wang, Jian-Zhong Tang, and Tao Bai

Development of Closed-Circuit Television Inspection Systemfor Steam Generators in Nuclear Power Plants . . . . . . . . . . . . . . . . . . . 550Chao-Rong Wu and Bo-Wen Lu

Research on the Security Technology of the Internet of Thingsin Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 556Hui-Hui Liang, Xin-Xin Gao, Wang-Ping Ye, and Wei Liu

A Study About Safety Technology of Control Systemand Information System in Nuclear Power Plant . . . . . . . . . . . . . . . . . . 563Jing Zhao, Chao Zhang, Zhe-Ming Liu, and Xia Yan

Author Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 569

Contents xiii

Analysis and Countermeasuresof Inconsistency for Acoustic Designand Lighting Design Regulations

and Standards in Main Control Roomof Nuclear Power Plant

Zhang Gang1(&), Zhao Jinbo2, Qi Kai3, Cheng Bo1, Mei Shibo1,and Wang Yan1

1 State Key Laboratory of Nuclear Power Safety Monitoring Technologyand Equipment, China Nuclear Power Engineering Co. Ltd.,

Shenzhen of Guangdong Prov. 518172, China{zhanggang,chengbo,meishibo,wangyan}@cgnpc.com.cn

2 Hejiu Office, CGN Power Co. Ltd., 518000 Shenzhen, Chinazhaojinbo@cgnpc.com.cn

3 Daya Bay Nuclear Power Operations and Management Co. Ltd.,518045 Shenzhen, Chinaqikai@cgnpc.com.cn

Abstract. Man-machine interface equipment in the MCR of NPP providessufficient monitoring information and control means for operators, and is thecontrol center. In order to ensure the safe and effective operation of NPP underall operating conditions, it is necessary to provide a favorable working envi-ronment for the staff of MCR to carry out the operation tasks of NPP.After studying and comparing the acoustic design and lighting design stan-

dard index and requirements of the main control room (MCR) of nuclear powerplants (NPPs) at home and abroad, analyzing the rationality for the imple-mentation requirements of the regulations and standards, analyzing the theo-retical for the noise and lighting, studying relevant experience feedback fromNPPs, the recommend index requirements has been put forward.Suggestions to modify the errors in some regulations and standards have been

put forward according to the design experience.

Keywords: Nuclear � Power plant � Main control room � Acoustic design �Lighting design � Regulations and standards � Experience review

1 Introduction

Based on the basic research results of ergonomics, physiology and psychology in acertain working environment, the environmental design of the MCR of NPP mainlyanalyses the interaction of operators, equipment and environment of MCR. The

© Springer Nature Singapore Pte Ltd. 2020Y. Xu et al. (Eds.): SICPNPP 2019, LNEE 595, pp. 1–8, 2020.https://doi.org/10.1007/978-981-15-1876-8_1

environment, equipment and conditions of the MCR are comprehensively designedbased on the factors of working efficiency, physical and mental health, human factorsengineering, human safety and comfort of the operators and function realization of theMCR.

Nuclear power regulation is a compulsory regulation formulated by the governmentto meet the minimum requirements of safety and environmental protection, and it haslegal effect. Nuclear power standards are non-mandatory documents formulated byindustry and approved by public organizations, which stipulate rules, guidelines andcharacteristics of nuclear power related work for the purpose of general use or reuse.This paper will analyze the inconsistencies of regulations and standards by comparingthe acoustic design and lighting design standards of NPPs at home and abroad,combining with the actual operation of NPPs and the experience feedback of operators,and put forward the recommended requirements of environmental indicators of theMCR.

2 Standard System of Environmental Design Lawsand Regulations for MCR

The main objectives of the environmental design of the MCR are as follows: (1) tomeet the requirements of the current applicable regulations, standards and norms; (2) toimprove the working environment level of operators and reduce the probability ofhuman error; (3) to improve the economic and safe operation level of NPPs; (4) to payattention to the occupational health level of operators and maintain their physical andmental pleasure.

In order to achieve the environmental design goal of the MCR, it is necessary tofocus on the analysis and research of the important factors in the environmental designof the MCR. The environmental design elements of the MCR mainly include acousticdesign, lighting design, ventilation design, interior design, color design and equipmentlayout design.

The current standards for nuclear power in China are basically transformed fromthe standards of the Institute of Electrical and Electronics Engineers (IEEE) and theInternational Electro Technical Commission (IEC). Although the contents are basicallycomplete, there are overlapping situations. These characteristics are also reflected in theenvironmental design standards of the NPP MCR.

For the environmental design of NPP MCR, the general key reference standards areshown in Table 1.

2 Z. Gang et al.

In the above regulations and standards, GB/T 13630-2015 is equivalent to IEC60964-2009; EJ/T 638-92 refers to ANSI/IEC 567; GB/T 22188-2000 and DL/T 575-1999 are equivalent or refer to ISO 11064-2000. Although a standard formulationstrategy based on IEC standards has established in China, Nureg-0700 have beenwidely used in the audit of nuclear safety review departments. So in the actual engi-neering design, Nureg-0700 also refers to frequently.

3 Requirements of Design Regulations and Standardsfor MCR and Analysis of Current Situation in OperatingPower Plant

This paper mainly analyses acoustic design and lighting design of the MCR,which arekey elements in the environment design.

3.1 Acoustic Design in MCR

Noise is one of the important factors that endanger human physical and mental health.Excessive noise in the MCR will interfere with the normal communication of operators,damage the physical and mental health of operators, affect their work, life and rest, andeven affect the normal and safe operation for NPPs.

Regulations and Standards Requirements. In domestic regulations HAF J0055-1995 [1] and EJ/T 638-92 [2], it is directly required that the background noise of thecontrol room should be no more than 45 dB(A), and the echo should be limited to lessthan 1 s. In GB/T 13630-2015 [3], it is required to refer to ISO 11064-6 [4], which isthe international general industrial standard. ISO 11064-6 requires that the backgroundnoise of the MCR should not exceed 45 dB(A), and the intermediate frequencyreverberation time should not exceed 0.75 s. In Nureg-0700 [5], the background noiseof the MCR should not be higher than 65 dB(A), and the reverberation time should belimited to less than 1 s.

Table 1. Regulations and standards for the environmental design in MCR

Standard number Standard title

HAF J0055-1995 Engineering principles for control room design of NPPGB/T 13630-2015 The design of control room of NPPGB/T 22188-2000 Ergonomic Design of Control CenterEJ/T 638-92 Design criteria for control room complex of NPPDL/T 575-1999 Guidelines for ergonomic design of control centresIEC 60964-2009 Design for control rooms of NPPsISO 11064-6-2000 Ergonomic design of control centres-Part 6: Environmental

requirements for control centresNureg-0700 Human-System Interface Design Review GuidelinesANSI/IEEE std 567 Design criteria for control room complex of NPP

Analysis and Countermeasures of Inconsistency for Acoustic Design 3

The requirement of noise and reverberation time in the MCR of NPP is basicallythe same as that in the control room of general industry, and the requirement is notmore than 45 dB(A). Nuclear Regulatory Commission of the United States has rela-tively low requirements for background noise indicators in the MCR of NPPs.

Current Situation in Operating Power Plants. According to the investigation, theaverage noise value of the MCR of the newer commercial N4 NPP in France is about65 dB(A), the average noise value of Ling’ao Unit 1 is 55 dB(A), the average noisevalue of Tianwan Unit 1 is 50–60 dB(A), and the average noise value ofCPR1000 NPP is 49 dB(A).

The background noise of the MCR in the NPPs investigated in the above inter-national scope does not meet the requirement of domestic laws and regulations that thebackground noise of the control room should be no more than 45 dB(A), and the gap islarge. In the design process for MCR of CPR1000 projects, the engineers absorbed a lotof experience feedback from domestic nuclear power units in operation, and continu-ously optimized each project. By adding a number of active and passive noisereduction methods, the background noise was reduced to less than 50 dB(A).According to the current design experience, if the background noise design indexcontinues to reduce below 45 dB(A), the requirements for technical, costs and scheduleof the project will increase significantly or even be unacceptable.

According to NUREG-0711 [6], the experience feedback of NPP operation is animportant method to solve the problems related to human factor engineering in powerplant. The experience feedback of the MCR operators from a NPP with an averagenoise value of 49 dB(A) in the MCR shows that the noise level of the MCR fully meetsthe operation requirements.

Analysis of Acoustic Environment Requirements for MCR. According to the rel-evant information of NPPs in operation in China, the main source of noise in MCR isair conditioning system. The computer and electronic instruments in MCR have noobvious contribution to noise. Because of the requirement of radiation protection inNPP, the atmospheric pressure in MCR is higher than that in the entrance and exitrooms, so the air supply volume is relatively large, and the wind pressure and speed arerelatively high, resulting in the larger noise in MCR. Compared with general industriessuch as thermal power and chemical industry, the noise of air conditioning system inMCR of NPP is greater.

Background noise should not impair verbal communication between any two pointsin the main operating area. Verbal communications should be intelligible using normalor slightly raised voice levels. Figure 1 shows the voice levels needed for spokencommunication over specified distances in the presence of different levels of back-ground noise.

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In the background noise level of 50 dB(A), the maximum distance of dialoguemeeting the normal communication requirements is about 5.5 m. If the speaker’s voiceis a little louder, the distance of dialogue can reach about 9 m. In normal operation ofNPP, the distance between operators in the MCR will not exceed 5 m, so as long as thebackground noise in the MCR of NPP is controlled below 50 dB(A), the normalcommunication of operators will not be affected.

After comparing domestic and foreign regulations and standards, and referring tothe operational experience feedback of NPPs, combined with the actual needs ofoperators in the MCR, it is reasonable that the background noise in the MCR is nothigher than 50 dB(A), which can meet the operational needs of the MCR of NPPs.

3.2 Lighting Design in MCR

The illumination levels of the MCR should meet the different illumination requirementsof each area of the MCR. At the same time, the shadows in the room should beeliminated and the reflections and glares should be minimized so as to alleviate thefatigue and sleepiness of the operator and reduce the probability of the operator makingmistakes due to the illumination defects. The MCR lighting system should includenormal lighting system and emergency lighting system. When normal lighting fails, itshould be automatically switched to emergency lighting, put into operation immedi-ately, and must work continuously for a certain period of time.

Regulations and Standards Requirements. In the domestic nuclear safety regula-tions HAF J0055-1995 [1], it is directly required that the average normal illuminationof MCR should be 100–500 lx, the accident illumination should be 50–100 lx for thedisplay screen, and the emergency lighting system illumination should be no less than200 lx. The nuclear industry standard EJ/T 638-92 [2] requires that the normal illu-mination of the sitting workstation should be 500–1000 lx and the minimum

Fig. 1. Voice level as a function of distance and ambient noise level

Analysis and Countermeasures of Inconsistency for Acoustic Design 5

illumination of the emergency lighting system should be 200 lx. In the ISO 11064-6[4], it is required that the illumination level of the working environment with writtenwork should be maintained at 200–750 lx. Nureg-0700 [5] claims that the illuminationlevel of the sitting workstation is 1000 lx, and the illumination of the control panel andthe general operating area is 500 lx.

In the regulations and standards, the illumination requirement is different foroperators’ workstations. In combination with the above standards, the normal illumi-nation 500 lx can meet most of the above standards. For emergency lighting, the claimsof all standards are the same and no less than 200 lx.

Current Situation in Operating Power Plants. Taking a NPP of CPR1000 project asan example, the MCR space is divided into five types of operation areas according to itsfunctional characteristics: main control area, surveillance area, auxiliary control area,passageway area and maintenance area, and some areas are overlapped. These fivetypes of regional functions are different, and the requirements of control degree are alsodifferent. Therefore, the MCR is divided into five illumination areas according to thenature and load intensity of different visual operations in different working areas of theMCR. The illumination in different areas is different. Detailed illumination zoningrefers to Fig. 2.

For the above NPP, under normal illumination, the average illumination of maincontrol area, surveillance area and auxiliary control area can reach more than 500–600 lx, the average illumination of channel area is about 400 lx, and the averageillumination of maintenance area is about 250 lx. The average emergency illuminationis over 200 lx. The experience feedback of the MCR operators from the above NPP

Fig. 2. MCR partition zoning for illumination

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shows that the illumination of the master control room fully meets the operationrequirements.

Analysis of Illumination Requirements for MCR. For the new nuclear power pro-jects in China, the illumination adjustment switch is fixed in the MCR. Therefore, thelighting design of the MCR can only consider the maximum illumination, and thecontrol of the actual illumination is left to the operators.

Combined with the operation experience feedback of CPR1000 NPPs, the normalillumination of the MCR can be continuously adjusted, the maximum illumination ofthe main operating areas such as workstations is not be less than 500 lx, the maximumillumination of the non-operating operating areas such as the passageway area and themaintenance area is not be less than 200 lx, and the emergency illumination is not beless than 200 lx, which can fully meet the operation requirements of the MCR.

4 Correct and Error Analysis of Environmental PartStandard Description of MCR

In the environmental design process of the MCR of NPP, some standard requirementshave been confusing for designers. With the accumulation of design experience, it isgradually recognized that there are errors in the requirements of some standards.

In HAF-J 0055 and EJ/T 638-92, the echo time of the MCR sound is required to beless than 1 s. In Nureg-0700, reverberation time in the MCR should be limited to lessthan 1 s. Echo is a single fixed reflection sound, its intensity and time difference arelarge enough to distinguish from direct sound, and can distinguish syllables. Rever-beration refers to the gradual attenuation of mixed reflective sound, which includesmultiple angles and arrivals at different times, after repeated diffuse reflection. Thelistener cannot distinguish any syllables. Echo is a kind of repetition of discontinuoussound, while reverberation is a kind of continuous fading out sound. Reverberationtime refers to the time required after the reverberation attenuation of 60 dB(A).A certain reverberation is beneficial to the sound quality. If the reverberation time is toolong, the sound will be ambiguous. Echoes can only destroy the sound quality andshould be avoided absolutely. At the same time, we consulted the original Nureg-0700standard text, “The acoustical treatment of the control room should limit reverberationtime to 1 s or less”, in which reverberation is interpreted as “混响” in physics, but alsomeans “回声”. In the process of compiling HAF-J 0055 and EJ/T 638-92, the editorrefers to Nureg-0700, but translates “reverberation” into “回声” by mistake, whichleads to standard description error.

In HAF-J 0055, the accident illumination to the display screen of the MCR is 50–100 lx. In IEC 60964-1989, the Incident illumination to the display screen of the MCRis required to be 50–100 lx. Incident means “入射” as well as “事故”. Incident illu-mination, especially as a phrase, means “入射照度”. In the process of compiling HAF-J0055, the editors may refer to IEC 60964-1989, but misinterpret “Incident” as “事故”.

Analysis and Countermeasures of Inconsistency for Acoustic Design 7

5 Concluding Remarks

The establishment of comfortable environment in the MCR, including acoustic designand lighting design, provides the operator with safe and comfortable working envi-ronment which meets the requirements of human factors engineering, ensures thehuman safety, physical and mental health and work comfort of the operator in theMCR, indirectly reduces the probability of the operator’s artificial misoperation, thusensuring the safe operation of the unit. Among the domestic and foreign regulationsand standards for the environmental design of the MCR of NPP, the problem ofinconsistent index parameters is prominent, which leads to different reference standardsfor engineering design and engineering acceptance, and affects the optimization andupgrading of environmental related system equipment and overall design scheme of theMCR. In this paper, the main acoustic design and lighting design standards of the MCRare analyzed. Based on the experience feedback from the operation of NPP, the rea-sonable and feasible index requirements are recommended, and the description errors insome standards are pointed out. It has reference significance for the optimization andimprovement of the environmental design of the MCR for the follow-up NPP project.

References

1. National Nuclear Safety Administration. Engineering principles for control room design ofnuclear power plant: HAF.J0055, 3 [S] (1995)

2. China National Nuclear Corporation. Design criteria for control room complex of nuclearpower plant, 3, 5–7 [S] (1992)

3. Standardization Administration of China. The design of control room of nuclear power plant:GB/T13630, 12 [S] (2015)

4. The International Organization for Standardization. Ergonomic design of control centres-Part6: Environmental requirements for control centres: ISO 11064-6, 18–19 [S] (2005)

5. U.S. Nuclear Regulatory Commission. Human-System Interface Design Review Guidelines(NUREG-0700, Rev. 2), 480–503 [S] (2004)

6. U.S. Nuclear Regulatory Commission. Human Factors Engineering Program Review Model(NUREG-0711, Rev. 2), 15 [S] (2004)

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Application of Mixed Reality Basedon Hololens in Nuclear Power Engineering

Yi Zhang(&), Dan Li, Hao Wang, and Zheng-Hui Yang

State Key Laboratory of Nuclear Power Monitoring Technology and EquipmentChina Nuclear Power Engineering Co., Ltd., Shenzhen, China

zhangyi52316@126.com

Abstract. With the continuous development of computer hardware and soft-ware technology, mixed reality has been emerged. It has been applied in manyindustries. However, the use in nuclear power engineering is little. The currentdesign data of nuclear power mainly uses 2D drawings and 3D models, which isnot conducive to collaborative design and design verification. In the mainte-nance process of Nuclear Power Plant, the staff has to carry the manual, andcan’t get real-time guidance. Teaching methods of technology and skill for staffsare a little boring and inefficient. It is possible to solve these problems by usingmixed reality with Hololens. The sharing feature of Hololens is helpful tocollaborative design. Rich holographic images and easy interactions of Hololenshelp maintenance workers get tasks done faster. The training system ofHPR1000 is developed, which provides the nuclear power staffs with the contentof HPR1000 plant layout and key equipments in the form of holographicimages.

Keywords: Mixed reality � Nuclear power plant � HPR1000 � Hololens

1 Application of MR in Nuclear Power Engineering

Virtual Reality (VR) is a computer simulation system that can create virtual worlds. Itis an interactive system simulation of 3D dynamic vision and physical behavior makingimmersive experience [1]. Augmented Reality (AR) is a technology that integrates real-world information with virtual world information. It applies virtual information to thereal world [2]. Mixed Reality Technology (MR), which includes augmented reality(AR) and virtual reality (VR), refers to a new visual environment created by thecombination of real and virtual world. Physical and digital objects coexist and interactin real time in a new visualization environment [3]. The technology enhances the user’srealism by creating an interactive feedback loop between the virtual world, the realworld and the user.

MR has been applied in many industries, but it has almost little relevant applica-tions in nuclear power plant. MR technology has great advantages in integrating virtualreality and reality. MR can bring virtual content into daily work, and it can solve theproblems encountered by employees in nuclear power plant work. As technologycontinues to mature, MR has a wide range of applications in the field of nuclear power.

© Springer Nature Singapore Pte Ltd. 2020Y. Xu et al. (Eds.): SICPNPP 2019, LNEE 595, pp. 9–20, 2020.https://doi.org/10.1007/978-981-15-1876-8_2

1.1 Design of Nuclear Power Engineering

The design of nuclear power plant is the first step in nuclear power project, involvingconstruction, civil engineering, machinery, electrical, instrument control, ventilationand fire protection. It has a wide variety of designs, complex tasks and high securityrequirements. The current common design method is still based on traditional 2Ddrawings, assisted with 3D data. It has the following disadvantages.

The 2D drawings can tell people the structural composition and related dimensionsof the device, but it is not possible to visually display the equipment. In the case of multi-person joint design, there are problems of understanding and communication difficulties.

Ordinary 3D data, although is capable of presenting a 3D design sense. However, it isincapable of providing immersion because itmust be run on aplatform such as a computer.

The verification of the design results requires the conversion of the design data intoa physical device model. The rationality of the design is verified by testing the physicaldevice. This method needs the construction of the physical equipment so that itincreases the economic cost and construction period of the project.

How to achieve what you see is what you get and what you get is the data is theproblem during the nuclear power design stage. Using mixed reality technology, thedesign results are virtualized and projected into the real environment by holographicprojection, as if the designs have been produced as real devices. The constructionprocess of the equipment model during the design verification process is eliminated.Designers do not need to face the miniature model in reality or the 3D model on thecomputer. They can see the nuclear power equipment and adjust the design influencewith different angles of view by wearing a HMD. According to results of the obser-vation, the irrationality and imperfections in the design can be found, and the designcan be optimized continuously. The use of mixed reality technology can reduce thetime period of design. In the nuclear power project, the problem will be solved at thedesign stage, reducing the risk of engineering construction.

1.2 Equipment Maintenance

Scheduled or non-scheduled maintenance of equipment is necessary during nuclearpower plant operation. In the maintenance process, the staff operates the nuclear powerequipment according to the maintenance manual. But there are some problems:

(1) Free of both hands

In the actual maintenance, the staff needs to take the manual to check the operationsteps, query the equipment data, and carry the tools to operate the equipment. This hasvery high requirements on the staff’s experience, operational proficiency and otherskills. The efficiency is low, which is easy to cause human error.

(2) Real-time guidance

The operator can carry out the operation step by step through the manual, but theposition of the work point needs the operator’s own judgment, which requires thestaff’s experience. It is also impossible to view the internal structure of the deviceduring the maintenance process, and it is easy to trigger the occurrence of an unknown

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problem. When encountering difficult problems that cannot be solved on the spot, it isdifficult to get help from the experts and obtain intuitive and clear guidance.

Using the mixed reality technology, after a nuclear power worker arrives at theoperation site, The worker can acquire 3D image of the device,enlarge the component,determine working point from multi-angle viewing by the MR device. The task list,security alerts, components of the device, manuals, operating procedures and processesof each component can be viewed through the virtual desktop. Nuclear power workersno longer need to carry any manuals and documents, freeing hands to perform oper-ations on the equipment. When faced with problems that cannot be solved on site, theMR device can transmit the live image back to the expert system in the backstage inreal time. The experts can view the situation on the spot, provide technical guidance,and provide remote support [4].

1.3 Staff Training

Nuclear power plant work has high risk. When performing a task, the staff needs to bevery familiar with the state of the equipment, the working principle of the system, andthe steps of the operation to ensure the correctness of the operation. If the wrongoperation is performed, the device may malfunction, and the system protection functionmay be activated by mistake, resulting in equipment damage, casualties, etc. Due to theimportance of nuclear safety, the skill training of nuclear power workers is particularlyimportant. Traditional document and video teaching can’t present stereoscopic effects.Teaching activities are mostly taught in training classrooms. There are many short-comings. Mixed reality technology can provide a new teaching model to improve thelearning efficiency of students [5]. It mainly has the following advantages:

(1) Intuitive

Mixed reality technology can present rich content in 2D and 3D. For the complexmechanical equipment of nuclear power, it is possible to establish 3D models to presentit to the students intuitively, and perform virtual disassembly of related equipment tohelp the trainees understand the internal structure.

(2) Reality

Mixed Reality technology is capable of projecting virtual objects into real environ-ments. The contents of teaching are virtual models that interact with real devices andenvironment.

(3) Mobility

The Mixed Reality Head-mounted Display is a stand-alone device that performsfunctions such as computing and image rendering and data storage independently,without connecting to other computers via cables. It is very convenient for students tostudy at anytime and anywhere.

Application of Mixed Reality Based on Hololens 11

2 Solutions of MR

Hololens is a MR head-mounted device developed by Microsoft Corporation. It isequipped with a holographic processing unit (HPU) to process real-time scanned data.Microsoft Hololens features holograms, high-definition lenses, stereo, and more,allowing you to see and hear holograms around you. In this article, Hololens is thehardware device in mixed reality solutions for nuclear power engineering.

2.1 Collaborative Design

At present, the Nuclear Power Design Institute has adopted some 3D layout designplatforms such as PDMS to create and manage 3D data. After the preliminary design iscompleted, the designer cannot visually check the design results. It is not conducive tothe continuous optimization of the design results. Hololens’ holographic images helpdesigners view design results from a 360° angle giving designers the same experienceas seeing real devices.

In practical applications, the model remains consistent with the real model in termsof structure and appearance. The model exported by PDMS which has no texture needsbe mapped according to the appearance of the real device. For a large plant layoutdesign, the number of models is large. When these models are used directly, theamount of data is too large, resulting in long processing time and low efficiency onHololens. In order to ensure that the system can run smoothly on Hololens, the modelneeds to be lightly processed. Since the models are usually composed of polygons, themodel is optimized by reducing the number of polygons while ensuring that the modelstructure is unchanged [6]. The two functions can be realized by using 3Ds Maxsoftware. After the optimization of the model is completed, the model can be importedinto Hololens for real-time viewing. Designers evaluate the design results throughHololens to identify deficiencies and make improvements in PDMS (see Fig. 1).

Creating modelsFactory layouts

PDMS

Model textureSimplifing model

3Ds Max

Holographic imageCollaborative design

HoloLens

Fig. 1. Solution for design

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When designers discuss a design, a Hololens device does not allow the designers toview the device model at the same time. There is a problem that information trans-mission is not timely, which is not conducive to mutual communication betweenmembers. Sharing feature of Hololens allows data sharing between multiple userswearing Hololens. It allows design team members to share design results. It enhancesthe communication between designers and improves the efficiency of the team. It isrealized by Anchor Sharing.

World Anchor provides a way to keep objects in their characteristic position androtation, ensuring the stability of holographic objects. It also provides the ability tomaintain the position of the holographic object in the real world. When you add a spaceanchor to a holographic object, you can accurately restore the hologram to its originalposition in the next steps. After Hololens scans the space environment, users canchoose to create some space anchors manually or by programming. The information ofthe space anchors can be serialized and passed to other Hololens. Each Hololens canreserialize this information and locate this space anchor in space. Here is the anchorsynchronization process (see Fig. 2).

Build server

Client Collect server

Local initialization of

anchor

Load anchor

Room identification in server

Synchronize room information

Download anchor data

Start

End

Y

N

Fig. 2. Anchor synchronization process

Application of Mixed Reality Based on Hololens 13

2.2 Intelligent Maintenance

The use of mixed reality technology in nuclear power maintenance mainly includes fiveaspects: room and equipment identification, prompting work points, interactive oper-ations, document viewing, and remote assistance (see Fig. 3).

(1) Room and equipment identification

Nuclear power plants have many factories. Maintenance workers are easy to go wrongwhen performing equipment maintenance. In order to prevent workers from operatingerrors, the following measures can be taken. Room number is set at the entrance to eachroom. Hololens identifies the number when a maintenance person wears a Hololensinto the room. Voice from Hololens prompts the worker the room number that he isgoing to enter. After the worker enters the room, Hololens can identify the equipmentthat needs to be repaired. The model of the equipment is loaded to facilitate the user toview the internal structure of the model.

(2) Prompting work points

Maintenance workers need to accurately determine the location of the operation and thecorrect tool when servicing the equipment. Hololens provides virtual prompt icons(such as arrows) to tell the operator the correct location. At the same time, the virtualmodel of tool is loaded to prompt the user the right tool. Hololens should determine thelocation of the device to achieve this function. Spatial mapping of Hololens can

Room and equipment

identification

prompting work points

Interaction

Document viewing

Remote Assistance

Preventing misalignment, loading virtual 3D models, viewing device structure

Scanning environment, positioning operation position

Gaze, voice, gestures

Obtaining maintenance manuals, equipment manuals

Video communication, remote expert guidance

Intelligent maintenance

Fig. 3. Structure of intelligent maintenance

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identify the surrounding environment and surface, establish spatial coordinate data ofthe room, and locate the equipment in the room. Here is the spatial mapping workflow(see Fig. 4).

(3) Interaction

Workers need to switch between various holographic images when using Hololensdevices. Hololens provides three interactive means: gaze, gestures, and voice.

Gaze is the first form of interaction which is used to locate objects. Its mainfunction is to tell the user the current focus [7]. It is achieved by a forward ray from theeyes of the user’s head. The ray can identify the object it is colliding with. In thedevelopment process, the camera is used to indicate the position and orientation of theuser’s head.

Start

Create surface viewer

Set spatial data range

Identify fixed areas Identify movable areas

Poll spatial surface information

Grid cache

Rendering

Handle surface changes (add, update, delete)

Create room data

Create spatial surface information

End

Handle asynchronous grid requests

Fig. 4. Spatial mapping workflow.

Application of Mixed Reality Based on Hololens 15

Gestures are the most central way to interact. With gaze, gestures are used to select,activate, and drag virtual objects [8]. The steps include: creating a gesture recognitioninstance, registering a gesture type, subscribing to a gesture event, starting gesturerecognition, and stopping gesture recognition.

Voice commands can reduce the number of UIs and optimize the UI interface. Bysetting keywords and corresponding behaviors for the application, when the userspeaks the keyword, the action of the budget is invoked [9]. The implementation stepsinclude: initializing the speech recognition instance by registering the keyword, andregistering the event as a response.

(4) Document viewing

When the maintenance workers are operating, they usually need to carry variousoperation manuals, which is not conducive to the liberation of hands. Hololens canstore a variety of documents, pictures, videos and other files for users to view. Itincludes but not limited to the following:

Equipment maintenance operation sheet, equipment maintenance procedure;System logic diagram, equipment manual, equipment maintenance manual;Historical maintenance record, relevant experience feedback;Equipment operating parameters;Operational video.

(5) Remote assistance

Video communication software can be installed on Hololens, such as skype. Workerscan conduct real-time video communication with experts on site. Experts can view thestatus of the device through a remote system so that they can help identify problems,and guide personnel to operate.

2.3 Training System for HPR1000

HPR1000 is China’s third-generation nuclear power technology with independentintellectual property rights. The nuclear power plant using this technology is currentlyunder construction. The HPR1000 design is guided by the defense in depth and theprinciple of reliability. For nuclear power workers, the technology needs to be re-learned.

In the current nuclear power related training system, there are many deficiencies.Firstly, the traditional 2D drawing and video teaching can’t give students an intuitivefeeling. For complex mechanical equipment structures, it is impossible to cut throughlayers so that students can’t deeply understand the internal structure of key equipment.The learning time is long and the training effect is poor. Secondly, using VR virtualreality technology, students can be provided with an immersive virtual learning envi-ronment. However, the current high performance VR helmet needs to be used with acomputer and has no mobility. Due to its opacity, it is impossible to combine the realenvironment and equipment on site, and the students are completely learning in thevirtual world and can’t use VR system in the front of equipment in factory. The current3D vertigo problem of VR helmets has severely shortened its use time and comfort.Thirdly, AR technology can superimpose virtual images onto real devices to achieve a

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