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
  • [41] A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
    Lee, Kwi Lim
    Ha, Kwi-Seok
    Jeong, Jae-Ho
    Choi, Chi-Woong
    Jeong, Taekyeong
    Ahn, Sang June
    Lee, Seung Won
    Chang, Won-Pyo
    Kang, Seok Hun
    Yoo, Jaewoon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (05) : 1071 - 1082
  • [42] A safety enhanced sodium-cooled MOX fueled fast reactor core concept
    Fujimura, Koji
    Fuchita, Sho
    Fujimata, Kazuhiro
    Takeda, Satoshi
    Takeda, Toshikazu
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2023, 60 (10) : 1258 - 1269
  • [43] Core geometry for recriticality prevention against CDA in sodium-cooled fast reactor
    Suetomi, Eiichi
    Nakano, Satoshi
    Takezawa, Hiroki
    Takaki, Naoyuki
    SPECIAL ISSUE OF FOR THE FIFTH INTERNATIONAL SYMPOSIUM ON INNOVATIVE NUCLEAR ENERGY SYSTEMS, 2017, 131 : 45 - 52
  • [44] REGRESSION MODEL FOR NUCLEAR CHARACTERISTICS OF SODIUM-COOLED FAST-REACTOR CORE
    KOBAYASHI, Y
    KONDO, S
    TOGO, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1975, 12 (01) : 61 - 63
  • [45] TRANSIENT SIMULATION ON REACTOR CORE MELT AND LOWER SUPPORT PLATE ABLATION IN IN-VESSEL RETENTION
    Chen, Xuyi
    Zhang, Xiaoying
    Xu, Junying
    Wang, Biao
    Zhan, Dekui
    Zhang, Huiyong
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 6, 2017,
  • [46] Transient Simulation on Reactor Core Melt and Lower Support Plate Ablation in In-Vessel Retention
    Chen X.
    Zhang X.
    Wang B.
    Xu J.
    Zhang L.
    Zhang H.
    Zhan D.
    Hedongli Gongcheng/Nuclear Power Engineering, 2017, 38 (06): : 51 - 56
  • [47] Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept
    Andriolo, Lena
    Meriot, Clement
    Bakouta, Nikolai
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2019, 5 (02):
  • [48] Experimental study on convectional heat transfer characteristics of argon space in the pool-type fast reactor vessel
    Yu, Zongyu
    Lu, Daogang
    Wang, Han
    Liu, Guangyao
    Feng, Yuheng
    Zhang, Xueyuan
    Ding, Xiao
    Xu, Haibo
    ANNALS OF NUCLEAR ENERGY, 2023, 188
  • [49] Real-time modeling of transient behavior of the primary coolant system in pool-type sodium cooled fast reactor
    Yu, Yang
    Guo, Fengchen
    Lu, Wei
    Wang, Xueqiang
    Sun, Zhuo
    ANNALS OF NUCLEAR ENERGY, 2022, 173
  • [50] Modeling of sodium-cooled fast reactor core-A sensitivity study on number of core channels and axial meshes
    Vikram, G.
    Riyas, A.
    Bachchan, Abhitab
    Rajendrakumar, M.
    Devan, K.
    Natesan, K.
    NUCLEAR ENGINEERING AND DESIGN, 2023, 403
12345