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
  • [1] Progress in Thermohydraulic Analysis of Accident Scenarios of a Water-Cooled Fusion Demo Reactor
    Nakamura, M.
    Watanabe, K.
    Tobita, K.
    Someya, Y.
    Tanigawa, H.
    Utoh, H.
    Sakamoto, Y.
    Araki, T.
    Asano, S.
    Asano, K.
    Kunugi, T.
    Yokomine, T.
    Gulden, W.
    2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE), 2015,
  • [2] Thermohydraulic Analysis of Accident Scenarios of a Fusion DEMO Reactor Based on Water-Cooled Ceramic Breeder Blanket: Analysis of LOCAs and LOVA
    Nakamura, M.
    Watanabe, K.
    Tobita, K.
    Someya, Y.
    Tanigawa, H.
    Utoh, H.
    Sakamoto, Y.
    Kunugi, T.
    Yokomine, T.
    Gulden, W.
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2016, 44 (09) : 1689 - 1699
  • [3] System analysis study for Korean fusion DEMO reactor
    Yeom, Jun Ho
    Kim, Keeman
    Lee, Young Seok
    Kim, Hyoung Chan
    Oh, Sangjun
    Im, Kihak
    Kessel, Charles
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 742 - 745
  • [4] Study of radiation limits in fusion reactor scenarios
    Becker, G
    NUCLEAR FUSION, 1999, 39 (07) : 937 - 948
  • [5] A preliminary conceptual design study for Korean fusion DEMO reactor
    Kim, Keeman
    Kim, Hyoung Chan
    Oh, Sangjun
    Lee, Young Seok
    Yeom, Jun Ho
    Im, Kihak
    Lee, Gyung-Su
    Neilson, George
    Kessel, Charles
    Brown, Thomas
    Titus, Peter
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 488 - 491
  • [6] Study of impacts on tritium breeding ratio of a fusion DEMO reactor
    Zheng, Shanliang
    Todd, Thomas N.
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1915 - 1918
  • [7] ENVIRONMENT AND SAFETY FEATURES OF A LASER FUSION REACTOR CONCEPT
    WALKER, PE
    JOURNAL OF THE OPTICAL SOCIETY OF AMERICA, 1978, 68 (04) : 546 - 546
  • [8] Analysis on Ex-Vessel Loss of Coolant Accident for a Water-Cooled Fusion Demo Reactor
    Watanabe, Kazuhito
    Nakamura, Makoto
    Tobita, Kenji
    Someya, Youji
    Tanigawa, Hisashi
    Utoh, Hiroyasu
    Sakamoto, Yoshiteru
    Araki, Takao
    Asano, Shiro
    Asano, Kazuhito
    2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE), 2015,
  • [9] Conceptual study of vertical sector transport maintenance for DEMO fusion reactor
    Utoh, Hiroyasu
    Tobita, Kenji
    Someya, Youji
    Takase, Haruhiko
    FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 1409 - 1413
  • [10] Study on containment safety systems for Korean fusion DEMO plant
    Oh, Kyemin
    Kang, Myoung-suk
    Heo, Gyunyoung
    Lee, Young-seok
    Kim, Hyoung-chan
    Moon, Young Tae
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 648 - 651