Preliminary Study on Core Melt In-vessel Retention of Pool-type Sodium-cooled Fast Reactor

被引：0
|
作者：
Xue, Fangyuan [1 ]
Zhang, Donghui [2 ]
Liu, Yizhe [1 ]
Zhang, Xisi [1 ]
机构：
[1] China Institute Of Atomic Energy, Beijing,102413, China
[2] CNNP Xiapu Nuclear Power Co., Ltd., Ningde,355199, China
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2024年 / 58卷 / 03期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：689 / 697
相关论文
共 50 条
  • [21] ZONED FUEL CORE FOR A SODIUM-COOLED FAST REACTOR
    MAHNA, KL
    NIMS, JB
    PAGE, EM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (02): : 581 - +
  • [22] Model Development and Transient Analysis of Thermal Stratification Phenomenon in Pool-Type Sodium-Cooled Fast Reactors
    Du P.
    Shan J.
    Deng J.
    Liu Y.
    Ding S.
    Chen W.
    Yuan P.
    Wu Z.
    Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (04): : 25 - 30
  • [23] Model development and transient analysis of thermal stratification phenomenon in pool-type sodium-cooled fast reactors
    Du, Peng
    Shan, Jianqiang
    Deng, Jian
    Xiong, Qingwen
    Li, Zhongchun
    Yuan, Peng
    ANNALS OF NUCLEAR ENERGY, 2022, 166
  • [24] An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors
    Lu, Cihang
    Wu, Zeyun
    Morgan, Sarah
    Schneider, James
    Anderson, Mark
    Xu, Liangyu
    Baglietto, Emilio
    Bucknor, Matthew
    Weathered, Matthew
    Bilbao y Leon, Sama
    NUCLEAR TECHNOLOGY, 2020, 206 (10) : 1465 - 1480
  • [25] Model development and transient analysis of thermal stratification phenomenon in pool-type sodium-cooled fast reactors
    Du, Peng
    Shan, Jianqiang
    Deng, Jian
    Xiong, Qingwen
    Li, Zhongchun
    Yuan, Peng
    Annals of Nuclear Energy, 2022, 166
  • [26] Design calculation and thermal-hydraulic analysis of 290 MW intermediate heat exchanger for pool-type sodium-cooled fast reactor
    Yu, Guang-Lei
    Li, Zeng-Yao
    APPLIED THERMAL ENGINEERING, 2020, 180
  • [27] CORE AND FUEL CYCLE FOR AN ADVANCED SODIUM-COOLED FAST REACTOR
    Poplavskii, V. M.
    Tsibulya, A. M.
    Khomyakov, Yu. S.
    Matveev, V. I.
    Eliseev, V. A.
    Tsikunov, A. G.
    Vasil'ev, B. A.
    Belov, S. B.
    Farakshin, M. R.
    ATOMIC ENERGY, 2010, 108 (04) : 260 - 266
  • [28] Core and fuel cycle for an advanced sodium-cooled fast reactor
    V. M. Poplavskii
    A. M. Tsibulya
    Yu. S. Khomyakov
    V. I. Matveev
    V. A. Eliseev
    A. G. Tsikunov
    B. A. Vasil’ev
    S. B. Belov
    M. R. Farakshin
    Atomic Energy, 2010, 108 : 260 - 266
  • [29] STRUCTURAL INTEGRITY RESEARCH FOR REACTOR PRESSURE VESSEL UNDER IN-VESSEL RETENTION OF A CORE MELT
    Gao, Yongjian
    He, Yinbiao
    Cao, Ming
    Li, Yuebing
    Bao, Shiyi
    Gao, Zengliang
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 1, 2016,
  • [30] Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
    Sasaki, Ryotaro
    Yamaji, Akifumi
    Uchimura, Kyota
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2023, 9 (02):
12345