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Produktbild: Progress of the Nuclear Power Safety and Advanced Reactor Technology in China
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Progress of the Nuclear Power Safety and Advanced Reactor Technology in China Volume 1

Aus der Reihe Lecture Notes in Energy

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Beschreibung

This open access book showcases China's progress in nuclear power safety and advanced reactor technology. Delving into critical topics such as safety improvements for currently operating reactors, advancements in new generation nuclear technologies, and the application of cutting-edge design and operational...

Beschreibung

This open access book showcases China's progress in nuclear power safety and advanced reactor technology. Delving into critical topics such as safety improvements for currently operating reactors, advancements in new generation nuclear technologies, and the application of cutting-edge design and operational safety measures, this book offers invaluable insights for professionals and researchers alike. Featuring illustrative diagrams, detailed tables, and clear explanations, it presents complex technical information in an accessible manner. The main benefit for readers lies in gaining a deep understanding of China's progress in nuclear energy innovation, equipping them with essential knowledge to navigate and contribute to the evolving global nuclear energy landscape. This book is essential reading for engineers, researchers, policymakers, and students interested in nuclear energy safety, technology development, and nuclear safety policy.

Portrait

Dr. Jipu Wang is an associate professor at Shenzhen University, specializing in reactor physics and nuclear facility decommissioning. He also serves as deputy dean of the College of Physics and Optoelectronic Engineering (CPOE) and deputy dean of the Institute for Advanced Study in Nuclear Energy & Safety (IASNES). He earned his doctorate from the University of Michigan and led verification and validation of the MPACT reactor physics code. He also contributed to the Molten Salt Reactor Experiment benchmark and led underwater reactor segmentation and packaging at EnergySolutions. He has published over 30 papers and was selected as an International Electrotechnical Commission (IEC) Young Professional representing China.
Hang Peng is a researcher-level senior engineer and Chief Scientist of China National Nuclear Corporation. He holds a master's degree from Chongqing University. Formerly Party Secretary and Director of the Design Research Institute at the Nuclear Power Institute of China, he specializes in nuclear power equipment, including drive mechanisms, pressure vessels, and process systems. He has led major research projects, received 40 provincial, ministerial and industry science and technology awards, holds 164 patents, and has published 42 papers. His honors include the State Council special government allowance and recognition as a Sichuan Provincial Expert with Outstanding Contributions.
Dr. Ming Yang is a professor at Shenzhen University and has served as a part-time professor and doctoral supervisor at Harbin Engineering University since 2018. He has also held appointments at Kyoto University and South China University of Technology. His research covers nuclear safety and reliability, digital instrumentation and control, and software reliability. He has led major research programs, published over 150 papers and three books, and served as an executive editor of the International Journal of Nuclear Safety and Simulation.
Qing Li is a researcher-level senior engineer and a Chief Engineer at the Nuclear Power Institute of China, responsible for reactor core nuclear design. He holds a master's degree from Tsinghua University and serves as Secretary-General of the Particle Transport Committee of the Chinese Society of Computational Physics. He has led major research projects, received a national-level science and technology progress award, and published over 50 papers.
Dr. Yong Liu is a distinguished professor and doctoral supervisor at Shenzhen University, where he serves as the dean of the Graduate School, dean of the IASNES, and director of the Shenzhen Key Laboratory of Nuclear and Radiation Safety. He is also a council member of the Chinese Nuclear Society. He has led dozens of research projects, including major and key national defense projects, projects funded by the National Natural Science Foundation of China, etc., with cumulative research funding exceeding RMB 150 million. He has published over 200 academic papers and holds over 50 granted Chinese invention patents. He has received two Second Prizes of the Hunan Provincial Science and Technology Progress Award and a Hunan Provincial Higher Education Teaching Achievement Award. He has extensive experience in scientific research and engineering practice in the fields of nuclear safety and radioactive waste management.
Dr. Zhengxi He is a researcher-level senior engineer and deputy director of the Design Research Institute at the Nuclear Power Institute of China. He holds a doctorate in Electronics and Information and specializes in instrumentation and control system design for nuclear power plants and research reactors. His honors include a Young Outstanding Innovator Award from the China Nuclear Energy Association.

Produktdetails

Einband

Gebundene Ausgabe

Erscheinungsdatum

13.04.2027

Abbildungen

Approx. 120 p.

Herausgeber Jipu Wang + weitere

Produktdetails

Einband

Gebundene Ausgabe

Erscheinungsdatum

13.04.2027

Abbildungen

Approx. 120 p.

Herausgeber
Verlag Springer Singapore
Seitenzahl

278

Maße (B/H)

15,5/23,5 cm

Sprache

Englisch

ISBN

978-981-9290-40-6

Herstelleradresse

Springer Nature Customer Service Center GmbH
Europaplatz 3
69115 Heidelberg
DE
ProductSafety@springernature.com

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  • Produktbild: Progress of the Nuclear Power Safety and Advanced Reactor Technology in China
  • Changes in the nuclear safety standard system before and after the Fukushima accident.- Achieving effective supervision of maintenance in nuclear power plants.- An overview of the lessons and experiences brought by the Fukushima accident on China’s energy and environmental policies.- Impacts on future nuclear power development plans, including nuclear export policies, pathways for next-generation reactor development, and the education of nuclear talent in universities.- The contribution of China’s nuclear energy development to the global nuclear energy field.- Active and passive cavity water injection system that significantly enhances the capability and safety in response to severe accidents in Generation III nuclear power plants.- Domestic design of the thermal-hydraulic system for the HPR1000.- Development of an online DNBR (Departure from Nucleate Boiling Ratio) monitoring system for the HPR1000.- Report on the three-dimensional flow field analysis inside the pressure vessel of the HPR1000.- The role of Level 1 Probabilistic Safety Assessment (PSA) in the improvement of the HPR1000 system for internal events.-Functional demonstration of the passive residual heat removal system on the secondary side of the HPR1000.- Research on the lateral flow of the ACP100 core.- Technological scheme and progress of the ACP100 modular small reactor and its demonstration project.- Research and development design of the ACP100S offshore floating nuclear power plant.- Research and development of ACP100 fuel assemblies.- Technical characteristics and safety evaluation of VVER AES-91.- Technical characteristics and safety evaluation of AP1000.- CAP1400 Technologies.- Research on unmanned control technology for reactors.- Digitalized reactor technology and progress.- A comprehensive review of the safety design for passive residual heat removal in advanced light water reactors.- Advancements in online risk monitoring technology for nuclear power plants.- Research on smart patrol for nuclear power plants.- Advancements in new safety analysis methods.- Progress in advanced simulation-driven risk-informed safety analysis techniques and their applications.- Research on nuclear safety strategies based on artificial intelligence technology.- Enhancing safety and cost-effectiveness of operating reactors through virtual reactor environments.- Technology for reactor decommissioning and the management of radioactive waste.- Artificial intelligence technology in the design and operation of nuclear energy systems.- Research on the Heat Transfer Limit of High-Temperature Heat Pipes with Curved Structures.- Study on Initiation Events and Operational Conditions Classification of Lead-Bismuth Fast Reactor.- Analysis of Strong Coupling Characteristics and Operational Schemes of Direct Cycle System in Reactor Power Plants.- Overview: Research Approaches for Future Advanced Reactors in China.- Sodium-cooled Fast Reactor System (SFR).- Analysis of Sodium-Air Heat Exchanger Technology Scheme Selection.- Power Conversion Systems Suitable for Sodium-cooled Fast Reactors.- Analysis of Small Liquid Metal Reactor Technology Routes.- Fusion Reactor Systems.