Phenomena Identification and Ranking Table for Thermal-Hydraulic Safety of China Fusion Engineering Test Reactor

被引:0
|
作者
Jiang, Jinghua [1 ]
Qin, Yuanchen [1 ]
Tong, Lili [1 ]
Cao, Xuewu [1 ]
Liu, Songlin [2 ]
Cheng, Xiaoman [3 ]
机构
[1] Shanghai Jiao Tong Univ, Sch Mech Engn, Shanghai 200240, Peoples R China
[2] Chinese Acad Sci, Hefei Inst Phys Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
[3] Hefei Comprehens Natl Sci Ctr, Inst Energy, Hefei 230031, Peoples R China
关键词
CFETR; phenomena identification and ranking table; safety analysis; HEAT-TRANSFER SYSTEM; OF-COOLANT ACCIDENT; EX-VESSEL LOCA; HYDROGEN BEHAVIOR; CODE DEVELOPMENT; VACUUM VESSEL; BLANKET; INGRESS; DESIGN; CONTAINMENT;
D O I
10.1080/15361055.2023.2271234
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The China Fusion Engineering Test Reactor (CFETR) is presently in the engineering design phase, and it is crucial to establish a thermal-hydraulic safety analysis method. First of all, the identification of phenomena in selected accident scenarios affecting reactor safety performance metrics should be focused on with the phenomenon identification and ranking table (PIRT), in which phenomena related to the thermal-hydraulic safety of the vacuum vessel and related systems are screened, including both design-basis accidents and beyond-design-basis accidents. The development of this PIRT exercise for CFETR thermal-hydraulic safety is addressed in this study; specifically, the importance ranking and stage of knowledge (SoK) of phenomena in the selected accidents are evaluated by the PIRT panel. The results of the PIRT analysis revealed that there exist certain safety-critical phenomena for which SoK is relatively low despite their perceived significance in safety performance metrics, which include the phase change of coolant, the migration of the multicomponent gas mixture, the migration of radionuclides within confinement, and the dispersion of gaseous radionuclides in the atmosphere. Ongoing research works and follow-up plans to improve the SoK of phenomena are presented.
引用
收藏
页码:960 / 975
页数:16
相关论文
共 35 条
  • [1] Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor
    Lei, Mingzhun
    Xu, Shuling
    Guo, Chao
    Liu, Sumei
    Song, Yuntao
    Lu, Kun
    Pei, Kun
    Xu, Kun
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (04) : 1657 - 1663
  • [2] Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor
    Zhou, Lei
    Zhang, Dalin
    Wang, Shibao
    Liu, Yapeng
    Wang, Chenglong
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2021, 157
  • [3] Thermal-Hydraulic Analysis and Optimization of HCPB Breeder Unit for Future Fusion Reactor
    Qi, Songsong
    Wang, Guodong
    Chen, Changqi
    Tang, Hongjun
    JOURNAL OF FUSION ENERGY, 2015, 34 (01) : 122 - 126
  • [4] Safety Analysis of China Fusion Engineering Test Reactor Helium Cooled Blanket
    Zhou B.
    Wang X.
    Wang Y.
    Hu B.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 : 29 - 32
  • [5] Preliminary thermal-hydraulic and safety analysis of China DFLL-TBM system
    Li, Wei
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    Jiao, Hong
    Bai, Yunqing
    Chen, Hongli
    Wu, Yican
    FUSION ENGINEERING AND DESIGN, 2013, 88 (05) : 286 - 294
  • [6] Preliminary thermal-hydraulic safety analysis of the 600 thermal megawatt dual fluid reactor
    Arnold, B.
    Hanusek, T.
    Liu, C.
    Nikitin, K.
    ANNALS OF NUCLEAR ENERGY, 2025, 213
  • [7] Thermal hydraulic analysis of China fusion engineering test reactor during thermal quenching by comparative approach of Relap5 and THEATRe codes
    Khan, Salah Ud-Din
    Song, Yuntao
    Khan, Shahab Ud-Din
    MODERN PHYSICS LETTERS B, 2016, 30 (30):
  • [8] DEVELOPMENT OF THERMAL-HYDRAULIC AND SAFETY ANALYSIS CODE FOR A HEAT PIPE COOLED REACTOR
    Jiao, Guanghui
    Xia, Genglei
    Zhou, Tao
    Wang, Jianjun
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 4, ICONE31 2024, 2024,
  • [9] Improvement of impinging jet heat transfer model for thermal-hydraulic analysis in the vacuum vessel of a fusion reactor
    Jiang, Jinghua
    Tong, Lili
    Cao, Xuewu
    FUSION ENGINEERING AND DESIGN, 2025, 214
  • [10] Activation calculation and radiation analysis for China Fusion Engineering Test Reactor
    Chen, Zhi
    Qiao, Shiji
    Jiang, Shuai
    Xu, X. George
    FUSION ENGINEERING AND DESIGN, 2016, 109 : 290 - 293