Advanced Search
BAI Ning, CHEN Yaodong, SHEN Feng, SUN Canhui, MENG Zhaocan, XING Mian, LI Xiaosheng, LI Lianrong. General Technology Proposal of Low-pressurized Heating Reactor HAPPY200[J]. Atomic Energy Science and Technology, 2019, 53(6): 1044-1050. DOI: 10.7538/yzk.2017.youxian.0566
Citation: BAI Ning, CHEN Yaodong, SHEN Feng, SUN Canhui, MENG Zhaocan, XING Mian, LI Xiaosheng, LI Lianrong. General Technology Proposal of Low-pressurized Heating Reactor HAPPY200[J]. Atomic Energy Science and Technology, 2019, 53(6): 1044-1050. DOI: 10.7538/yzk.2017.youxian.0566
shu

General Technology Proposal of Low-pressurized Heating Reactor HAPPY200

  • State Power Investment Central Research Institute, Beijing 102209, China

More Information
    Graphical Abstract
    • Abstract
  • Aiming at a safe, economic and mature nuclear heating system, a low pressurized heating reactor HAPPY200 was developed. The general scheme, key parameters, core scheme, thermal-hydraulic design, structure scheme, main process system scheme, equipment scheme and safety evaluation of the HAPPY200 were designed and analyzed. A safety system based on large volume tank was used by HAPPY200, which provided passive safety for reactor system. The technical scheme of HAPPY200 has the characteristics of high security, simplified system, mature technology, short construction period, low cost of operation and maintenance and high quality of heating. It has a broad market prospect and market competitiveness. At present, the conceptual design of HAPPY200 was completed and the site of demonstration reactor was identified. Engineering design is being carried out.
    • FullText(HTML)
    • References (17)
  • [1]
    孙恩慧，李岩，赖小圭，等. 关于在我国北方农村地区开展集中供暖的调查研究[J]. 科技创新与应用，2013（9）：22-23.
    [2]
    LIANG Xuan, ZOU Tao, GUO Bin, et al. Assessing Beijing’s PM2.5 pollution: Severity, weather impact, APEC and winter heating[C]∥Proceedings of the Royal Society: A Mathematical Physical & Engineering Sciences. [S. l.]: [s. n.], 2015.
    [3]
    王大中，马昌文，董铎，等. 自然循环一体化式低温供热堆[J]. 核动力工程，1988，9(1)：1-5.WANG Dazhong, MA Changwen, DONG Duo, et al. The integrated natural circulation district heating reactor[J]. Nuclear Power Engineering, 1988, 9(1): 1-5(in Chinese).
    [4]
    郑文祥，董铎. 5 MW低温核供热试验堆及其安全特性[J]. 原子能科学技术，1990，24(6)：30-36.ZHEN Wenxiang, DONG Duo. 5 MW low temperature nuclear heating test reactor and safety characteristics[J]. Atomic Energy Science and Technology, 1990, 24(6): 30-36(in Chinese).
    [5]
    王大中，董铎，郑文祥. 5 MW低温核供热堆的研制和运行特性[J]. 清华大学学报：自然科学版，1991，31(3)：1-11.WANG Dazhong, DONG Duo, ZHEN Wenxiang. Development and operation characteristics of 5 MW low temperature nuclear heating reactor[J]. Journal of Tsinghua University: Natural Science Edition, 1991, 31(3): 1-11(in Chinese).
    [6]
    核电厂安全：设计，IAEA-SSR2-1[R]. 维也纳：国际原子能机构，2016.
    [7]
    WANG Fangnian, CHEN Yaodong, BAI Ning, et al. Shape characteristics and condensation heat transfer of supersonic steam jet in subcooled water[C]∥Proceedings of the 2017 25th International Conference on Nuclear Engineering. Shanghai: [s. n.], 2017.
    [8]
    白宁，朱元兵，任志豪，等. 子通道分析程序LINDEN的开发与初步验证[J]. 原子能科学技术，2013，47(增刊)：299-301.BAI Ning, ZHU Yuanbing, REN Zhihao, et al. Development and verification of sunchannel analysis code LINDEN[J]. Atomic Energy Science and Technology, 2013, 47(Suppl.): 299-301(in Chinese).
    [9]
    白宁，朱元兵，任志豪，等. 适用于PWR燃料组件的CHF关系式的开发及评估[J]. 原子能科学技术，2013，47(增刊)：394-397.BAI Ning, ZHU Yuanbing, REN Zhihao, et al. Development and assessment of CHF correlation for PWR fule assembly[J]. Atomic Energy Science and Technology, 2013, 47(Suppl.): 394-397(in Chinese).
    [10]
    孙灿辉，张迪，白宁，等. 反应堆低压临界热流关系式评价[C]∥北京核学会第十二届（2016年）核应用技术学术交流会文集. 北京：北京核学会，2016.
    [11]
    BAI Ning, ZHU Yuanbing, REN Zhihao, et al. The principle and preliminary validation of a new subchannel code[C]∥Proceedings of the 2013 21st International Conference on Nuclear Engineering. Chengdu: [s. n.], 2013.
    [12]
    BAI Ning, LIU Wei, ZHU Yuanbing, et al. The development and assessment of a new CHF correlation for PWR fuel assemblies[C]∥Proceedings of the 2013 21st International Conference on Nuclear Engineering. Chengdu: [s. n.], 2013.
    [13]
    SUN Canhui, BAI Ning, ZHANG Di, et al. Analysis of thermal-hydraulic behavior for reduced-height PWR fuel assemblies[C]∥NURETH17. [S. l.]: [s. n.], 2017.
    [14]
    朱继洲. 压水堆核电站的运行[M]. 北京：原子能出版社，2000.
    [15]
    Nuclear Safety Analysis Division. RELAP5/MOD3.4 code manual, Volume 1[R]. USA: NRC, 2001.
    [16]
    XING Mian, BAI Ning, CHEN Yaodong, et al. Preliminary LOCA analysis of heating-reactor of advanced low-pressurized and passive safety system (HAPPY)[C]∥Proceedings of the 2017 25th International Conference on Nuclear Engineering. Shanghai: [s. n.], 2017.
    [17]
    XING Mian, CHEN Yaodong, BAI Ning, et al. Preliminary SBO analysis of heating-reactor of advanced low-pressurized and passive safety system (HAPPY)[C]∥NURETH17. [S. l.]: [s. n.], 2017.
    • Related Articles

Catalog

    Get Citation
    PDF
    XML
    Article views (454) PDF downloads (1247) Cited by()
    Turn off MathJax
    Article Contents
    Abstract
    References
    Links

    Website Copyright©2023 Atomic Energy Science and Technology  京ICP备12043220号-2

    Address：Box 65, P.O. Box 275, Beijing   Postal Code：102413

    Email：yznkxjs7285@163.com   Tel:（010）69357285,69358024

    Supported by: Beijing Renhe Information Technology Co., Ltd.  Baidu Analytics

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return