Study of safety features and accident scenarios in a fusion DEMO reactor

被引:15
|
作者
Nakamura, M. [1 ]
Tobita, K. [1 ]
Gulden, W. [2 ,3 ]
Watanabe, K. [1 ,4 ]
Someya, Y. [1 ]
Tanigawa, H. [5 ]
Sakamoto, Y. [1 ]
Araki, T. [4 ]
Matsumiya, H. [4 ]
Ishii, K. [4 ]
Utoh, H. [1 ]
Takase, H. [6 ]
Hayashi, T. [5 ]
Satou, A. [7 ]
Yonomoto, T. [7 ]
Federici, G. [2 ,3 ]
Okano, K. [6 ]
机构
[1] Japan Atom Energy Agcy, Rokkasho, Aomori 0393212, Japan
[2] EFDA Garching, Fus Energy, D-85748 Garching, Germany
[3] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[4] Toshiba Co Ltd, Yokohama, Kanagawa 2358523, Japan
[5] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan
[6] IFERC Project Team, Rokkasho, Aomori 0393212, Japan
[7] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan
关键词
DEMO; Safety; Source term analysis; Accident scenario analysis; DESIGN;
D O I
10.1016/j.fusengdes.2014.04.062
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
After the Fukushima Dai-ichi nuclear accident, a need for assuring safety of fusion energy has grown in the Japanese (JA) fusion research community. DEMO safety research has been launched as a part of Broader Approach DEMO Design Activities (BA-DDA). This paper reports progress in the fusion DEMO safety research conducted under BA-DDA. Safety requirements and evaluation guidelines have been, first of all, established based on those established in the Japanese ITER site invitation activities. The radioactive source terms and energies that can mobilize such source terms have been assessed for a reference DEMO concept. This concept employs in-vessel components that are cooled by pressurized water and built of a low activation ferritic steel (F82H), contains solid pebble beds made of lithium-titanate (Li2TiO3) and beryllium titanium (Be12Ti) for tritium breeding and neutron multiplication, respectively. It is shown that unlike the energies expected in ITER, the enthalpy in the first wall/blanket cooling loops is large compared to the other energies expected in the reference DEMO concept. Reference accident event sequences in the reference DEMO in this study have been analyzed based on the Master Logic Diagram and Functional Failure Mode and Effect Analysis techniques. Accident events of particular concern in the DEMO have been selected based on the event sequence analysis and the hazard assessment. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:2028 / 2032
页数:5
相关论文
共 50 条
  • [41] Simulation study of tritium atmospheric dispersion of loss of vacuum accident of a fusion reactor
    Jiang J.
    Cao X.
    He Jishu/Nuclear Techniques, 2023, 46 (02):
  • [42] SEVERE ACCIDENT SCENARIOS AT ISSUE IN DOE PLAN TO RESTART REACTOR
    SWEET, W
    PHYSICS TODAY, 1991, 44 (11) : 78 - 81
  • [43] Safety goals for a fusion reactor
    Saji, G
    FUSION ENGINEERING AND DESIGN, 2003, 69 (1-4) : 631 - 636
  • [44] Safety Analysis of Accident Scenarios for the HTR-10
    高祖瑛
    蒋志强
    李宝琰
    王春云
    TsinghuaScienceandTechnology, 1996, (01) : 27 - 31
  • [45] Maximal design basis accident of fusion neutron source DEMO-TIN
    B. N. Kolbasov
    Physics of Atomic Nuclei, 2015, 78 : 1128 - 1133
  • [46] Maximal Design Basis Accident of Fusion Neutron Source DEMO-TIN
    Kolbasov, B. N.
    PHYSICS OF ATOMIC NUCLEI, 2015, 78 (10) : 1128 - 1133
  • [47] Adaptation of the ASTEC code system to accident scenarios in fusion installations
    Seropian, C.
    Barrachin, M.
    Van Dorsselaere, J. P.
    Vola, D.
    FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 2698 - 2703
  • [48] Performance Analysis of the NbTi PF Coils for the EU DEMO Fusion Reactor
    Zappatore, Andrea
    Bonifetto, Roberto
    Bruzzone, Pierluigi
    Corato, Valentina
    Di Zenobio, Aldo
    Savoldi, Laura
    Sedlak, Kamil
    Turtu, Simonetta
    Zanino, Roberto
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2018, 28 (04)
  • [49] On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor
    Moscato, Ivo
    Barucca, Luciana
    Ciattaglia, Sergio
    Di Maio, Pietro Alessandro
    36TH UIT HEAT TRANSFER CONFERENCE, 2019, 1224
  • [50] Fusion Specific Features in ITER Accident Analysis
    H.-W. Bartels
    C. W. Gordon
    S. J. Piet
    A. E. Poucet
    G. Saji
    L. N. Topilski
    Journal of Fusion Energy, 1997, 16 : 3 - 10