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  1. No Access

    Chapter and Conference Paper

    Closed-Loop Management Optimization of Technical Change in PWR Nuclear Power Plant

    In the process of construction and commissioning of million kilowatt pressurized water reactor (CPR1000), due to design optimization or technical parameter adjustment, there will be a certain amount of technic...

    Min Long, Fang Li, Li-Chuang Tian in Nuclear Power Plants: Innovative Technolog… (2021)

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    Chapter and Conference Paper

    The Analysis for Method of I&C Equipment Period Demonstrating in NPP Refueling Cycle Extension Project

    Before the implementation of the extended fuel cycle improvement in nuclear power plants, it is necessary to conduct an adaptive analysis of the relevant systems and equipment cycles. The purpose is to show th...

    Zhi-Wu Guo, Long-Qiang Zhang in Nuclear Power Plants: Innovative Technolog… (2021)

  3. No Access

    Chapter and Conference Paper

    Optical Fiber Communication and Wireless Communication Technology Oriented to Internet of Things

    The technology of Internet of things based on RFID has begun to play an increasingly important role in modern communication. according to the characteristics of system communication is an emerging networking t...

    **ao-Chen Yang, Zhen-Yu Yan, Zeng-Jun Chun in Nuclear Power Plants: Innovative Technolog… (2021)

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    Chapter and Conference Paper

    Effects of Normal Load, Thickness of Oxide Layer and Number of Cycles on Fretting Wear of PWR Fuel ROD Cladding

    Fretting wear and corrosion experiments are carried out under a simulative primary circuit environment provided by autoclave, the loss of volume of zirconium alloy fuel rod cladding samples under different nor...

    Li Dongxing, Hu Yong, Wang Hui, **n Long in Proceedings of the 23rd Pacific Basin Nucl… (2023)

  5. Chapter and Conference Paper

    Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular Reactor

    On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized water reactor nuclear power plants, the principle of setting f...

    Ming-ming **a, Jun-long Wang, Tao Xu in Proceedings of the 23rd Pacific Basin Nucl… (2023)

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    Chapter and Conference Paper

    Study on 131I Source Term in Reactor Coolant Under Shutdown Transient Condition

    131I activity in coolant under transient conditions is an important input for SGTR accident source term analysis in nuclear power plant, which directly affects whether the radioactive consequences of SGTR can mee...

    **g Fu-ting, L. V. Huan-wen in Proceedings of the 23rd Pacific Basin Nucl… (2023)

  7. Chapter and Conference Paper

    Study and Resolution of Pressurizer Pressure Great Fluctuation Problem in CRP1000 RGL04 Test

    RGL04 Test is the highest risky test during CPR1000 power operation,which is difficult to control the state and easily results in house load, turbine trip and reactor trip. Pressurizer pressure great fluctuati...

    Kai Wang, Bing-wen Li, Ming-jia Zhou in Proceedings of the 23rd Pacific Basin Nucl… (2023)

  8. Chapter and Conference Paper

    Analytical Method Research of Source Term for Steam Generator Tube Rupture Accident of Small Modular Reactor

    Based on the full reference to the existing engineering practice and safety review experience, and considering the actual design characteristics of the small modular reactor ACP100, a set of source term analys...

    Ming-ming **a, Jun-long Wang, Jian-** Zhu in Proceedings of the 23rd Pacific Basin Nucl… (2023)

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    Chapter and Conference Paper

    Design and Experimental Study of Ultra High Pressure Water Jet Decontamination Device

    When nuclear facilities are overhauled or decommissioned, a high-pressure water jet removes radioactive contamination from the project site. During that process, a large amount of water needs to be used for be...

    Chengtian Zhang, Lei Teng, **san Chen in Proceedings of the 23rd Pacific Basin Nucl… (2023)

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    Chapter and Conference Paper

    Experimental Study on Pool Boiling Heat Transfer Characteristics of SiC Cladding Under Atmospheric Pressure

    Since the Fukushima accident in Japan, Accident-Tolerant Fuel (ATF) was investigated to mitigate the zircaloy-water oxidation reaction at a high temperature. Silicon carbide (SiC) cladding is one of the most p...

    **ng Lei, Qing-long Wen, Zhen-xun Peng in Proceedings of the 2023 Water Reactor Fuel… (2024)