厦门大学学者库

学者信息

郑剑香 (JianXiang Zheng)

能源学院

按发表年份分组
2024
2023
2022
2021
2019
按发表刊物分组
合作者

已发表成果：

WOK 论文 22 篇;中文核心 5 篇;其它论文 3 篇;专利发明 11 个;

  • Myrmecia: Failure analysis and thermodynamic coupled simulation program for heat pipe in micro reactor based on MOOSE

    Nuclear Engineering and Design,0029-5493,2024-03.
    Wei, Kun; Zhang, Shuaishuai; Zheng, Jianxiang; Yu, PeiZhao; Miao, Huifang
    WOS:001171353700001   EI:20240515451145   10.1016/j.nucengdes.2024.112939
    收录情况：SCIE、EI

  • An Integrated Solution for Nuclear Power Plant On-Site Optimal Evacuation Path Planning Based on Atmospheric Dispersion and Dose Model

    SUSTAINABILITY,,2024-03.
    Ren, Yushuo; Zhang, Guoming; Zheng, Jianxiang; Miao, Huifang
    WOS:001192826800001   10.3390/su16062458
    收录情况：SCIE、SSCI

  • Myrmecia: Failure Analysis and Thermodynamic Coupled Simulation Program for Heat Pipe in Micro Reactor Based on Moose

    SSRN,1556-5068,2023-10-13.
    Wei, Kun (1); Zhang, ShuaiShuai (1); Zheng, JianXiang (1); Miao, Huifang (1)
    EI:20230365086   10.2139/ssrn.4601460
    收录情况：EI

  • Dynamic Dose-Based Emergency Evacuation Model for Enhancing Nuclear Power Plant Emergency Response Strategies

    Energies,,2023-09.
    Miao, Huifang; Zhang, Guoming; Yu, Peizhao; Shi, Chunsen; Zheng, Jianxiang
    WOS:001063705700001   EI:20233714718319   10.3390/en16176338
    收录情况：SCIE、EI

  • REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents

    Nuclear Technology,0029-5450,2023.
    Shi, Chunsen; Li, Jun; Zheng, Jianxiang; Zhang, Jian; Cao, Liuxuan; Miao, Huifang
    WOS:001083660300001   EI:20234214908659   10.1080/00295450.2023.2264515
    收录情况：SCIE、EI

  • Optimization strategy for SAM in nuclear power plants based on NSGA-II

    Kerntechnik,0932-3902,2023.
    Zhou, Sikai; Xie, Mingliang; Zheng, Jianxiang; Miao, Huifang
    WOS:001099929900001   EI:20234515039561   10.1515/kern-2023-0036
    收录情况：SCIE、EI

  • Machine Learning-Based Prediction of Irradiation-Induced Swelling from Synergistic Effects of Helium and Hydrogen

    Fusion Science and Technology,1536-1055,2023.
    Jin, Huajiang; Zhang, Shuaishuai; Zheng, Jianxiang; Zhang, Jian; Miao, Huifang; Cao, Liuxuan
    WOS:001061465100001   EI:20233714699963   10.1080/15361055.2023.2232229
    收录情况：SCIE、EI

  • Anomalous temperature dependence of ion transport under osmotic pressure in graphene oxide membranes

    2D MATERIALS,2053-1583,2022-10-01.
    Lin, Lingxin; Liu, Chang; Ma, Pengfei; Zhao, Zeyuan; Chen, Jianming; Zhao, Danting; Wei, Shiqi; Zhe...
    WOS:000828347200001   EI:20223112459236   10.1088/2053-1583/ac7ecd
    收录情况：SCIE、EI

  • Transient heat transfer analysis of double-layer molten pool under severe accident

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY,0022-3131,2022-02.
    Ma, Pengfei; Liu, Chang; Liu, Yan; Liu, Hui; Xue, Jiyuan; Zhao, Danting; Zheng, Jianxiang; Cao, Liu...
    WOS:000753312700001   EI:20220811695396   10.1080/00223131.2021.2023368
    收录情况：SCIE、EI

  • A study of RCS depressurization strategy of CPR1000 SAMG

    KERNTECHNIK,0932-3902,2022-02.
    Yu, Peizhao; Zheng, Jianxiang; Li, Jun; Miao, Huifang; Wu, Ling; Gu, Danying
    WOS:000758591700001   EI:20221111771333   10.1515/kern-2021-1055
    收录情况：SCIE、EI

  • Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident

    Kerntechnik,0932-3902,2021-06-01.
    Wu, L.; Miao, H.; Yu, P.; Huang, Z.; Zheng, J.; Li, J.; Zhai, Z.; Jia, T.
    WOS:000663551900001   EI:20212610563201   10.1515/kern-2021-0005
    收录情况：SCIE、EI

  • Development of optimization platform and its application in severe accident management

    Progress in Nuclear Energy,0149-1970,2021-06.
    Wu, Ling; Yu, Peizhao; Huang, Zhi'ao; Li, Jun; Zheng, Jianxiang; Wang, Junlong; Xu, Tao; Gao, Yuxua...
    WOS:000656899500002   EI:20211610219439   10.1016/j.pnucene.2021.103721
    收录情况：SCIE、EI

  • Nuclear power technology training based on mixed reality technology

    Transactions of the American Nuclear Society,0003-018X,2019.
    Chen, Yifen (1); Zheng, Jianxiang (1); Hsieh, Huai-En (1); Wu, Yichun (1)
    EI:20204109330880  
    收录情况：EI

  • Simulation of hydrogen generated from fuel bundles and verification of a semi-empirical cladding oxidation model by PWR type CORA tests

    Progress in Nuclear Energy,0149-1970,2018-03.
    Ni, Xinghe(1); Wong, Kin-Wah(1); Zheng, Jianxiang(1); Li, Ning(1)
    WOS:000423248000019   EI:20175004533586   10.1016/j.pnucene.2017.11.020
    收录情况：SCIE、EI

  • Analysis of deficiencies in current prediction method for hydrogen generated from fuel cladding and potential improvement approaches

    Nuclear Engineering and Design,0029-5493,2018-01.
    Ni, Xinghe(1); Chen, Yifen(1); Wang, Jun(2); Zheng, Jianxiang(1); Miao, Huifang(1); Huang, Zijing(1...
    WOS:000425301100023   EI:20174704448553   10.1016/j.nucengdes.2017.11.012
    收录情况：SCIE、EI

  • Development of a semi-empirical cladding oxidation model and verification by BWR & VVER type CORA tests

    Nuclear Engineering and Design,0029-5493,2017-07-01.
    Ni, Xinghe(1); Wong, Kin-Wah(1); Wu, Jingjin(2); Zheng, Jianxiang(1); Li, Ning(1)
    WOS:000403525400018   EI:20171903647832   10.1016/j.nucengdes.2017.04.007
    收录情况：SCIE、EI

  • A DEVELOPMENT OF HUMAN-SYSTEM INTERACTION IN DIGITAL NPPS

    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 1,,2017 .
    Lu, Jiachuan; Liao, Longtao; Feng, Bo; Chen, Yifen; Hao, Junwei; Ye, Kai; Zheng, Jianxiang
    WOS:000426019800078   EI:20174404360658   10.1115/ICONE2567212
    收录情况：EI、CPCI-S

  • Simulation of early phase radioactivity of CPR1000 plant under LOCAs based on RELAP5-3D core engineering simulator

    PROGRESS IN NUCLEAR ENERGY,0149-1970,2016-11.
    Ni, Xinghe; Zheng, Jianxiang; Hou, Entong; Hao, Junwei; Bian, Boshen; Li, Ning
    WOS:000386401700004   10.1016/j.pnucene.2016.07.019
    收录情况：SCIE

  • Development, verification and validation of an FPGA-based core heat removal protection system for a PWR

    Nuclear Engineering and Design,0029-5493,2016-05.
    Wu, Yichun(1); Shui, Xuanxuan(1); Cai, Yuanfeng(1); Zhou, Junyi(1); Wu, Zhiqiang(2); Zheng, Jianxia...
    WOS:000375405400026   EI:20161502228220   10.1016/j.nucengdes.2016.03.018
    收录情况：SCIE、EI

  • Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator

    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS,1687-6075,2016.
    Hao, Junwei; Zhang, Yaoli; Zheng, Jianxiang; Zhou, Zhiwei; Sheng, Xuanyu; Hong, Gang; Ye, Kai; Li, ...
    WOS:000390553500001   10.1155/2016/3071686
    收录情况：SCIE

  • The Framework of Nuclear Management Information System

    EMERGING RESEARCH IN WEB INFORMATION SYSTEMS AND MINING,1865-0929,2011.
    Cai, Gangquan(1); Chen, Shaomin(1); Zheng, Jianxiang(1); Miao, Huifang(1)
    WOS:000310766500037   EI:20114114417656   10.1007/978-3-642-24273-1_37
    收录情况：EI、CPCI-S

  • Effective software verification and validation approach for nuclear power plant digital instrumentation and control systems

    International Conference on Nuclear Engineering, Proceedings, ICONE,,2010.
    Yang, Steve(1); Ding, Jun(2); Miao, Huifang(2); Zheng, Jianxiang(2)
    EI:20114014385748   10.1115/ICONE18-29264
    收录情况：EI

  • 核事故缓解任务的最优工作路径算法研究

    厦门大学学报(自然科学版),0438-0479,2023-07-31.
    施纯森;郑剑香;缪惠芳
    CSCD扩展库

  • 核事故缓解任务的最优工作路径算法

    厦门大学学报(自然科学版),0438-0479,2023-07-31.
    施纯森;郑剑香;缪惠芳
    CSCD扩展库

  • CPR1000全厂断电叠加小破口事故下一回路外部注水策略分析

    厦门大学学报(自然科学版),0438-0479,2019-04-29.
    陈艺芬;黄志翱;郑剑香;缪惠芳
    CSCD核心

  • CPR1000全厂断电叠加小破口失水事故下一回路外部注水策略分析

    厦门大学学报(自然科学版),0438-0479,2019-04-29.
    陈艺芬;黄志翱;郑剑香;缪惠芳
    CSCD核心

  • 基于3Keymaster平台的压水堆核电站系统回路放射性仿真研究

    核科学与工程,0258-0918,2016-04-15.
    郑剑香;倪星河;谢珊;何明
    CSCD核心 CSCD核心 理工二类核心

  • 通过pH值调节圆柱形纳米孔进行压力驱动的离子分离

    粘接,1001-5922,2022-10-15.
    许梦伊;郑剑香

  • 基于Modelica语言的压水堆稳压器建模及其仿真

    仪器仪表用户,1671-1041,2016-04-08.
    郑剑香;郝俊伟;边博深

  • 低碳氨发动机的研究

    可再生能源,1671-5292,2014-10-20.
    胡剑全;谢珊;吴一纯;郑剑香;梅文中