Key Aspects of the Safety Study of a Water-Cooled Fusion DEMO Reactor

• NAKAMURA Makoto

  Japan Atomic Energy Agency, Rokkasho

• TOBITA Kenji

  Japan Atomic Energy Agency, Rokkasho

• SOMEYA Youji

  Japan Atomic Energy Agency, Rokkasho

• TANIGAWA Hisashi

  Japan Atomic Energy Agency, Naka

• GULDEN Werner

  Fusion for Energy, c/o EFDA Garching and Max-Plank-Institut fuer Plasmaphysik

• SAKAMOTO Yoshiteru

  Japan Atomic Energy Agency, Rokkasho

• ARAKI Takao

  Toshiba Corporation

• WATANABE Kazuhito

  Toshiba Corporation

• MATSUMIYA Hisato

  Toshiba Corporation

• ISHII Kyoko

  Toshiba Corporation

• UTOH Hiroyasu

  Japan Atomic Energy Agency, Rokkasho

• TAKASE Haruhiko

  IFERC Project Team

• HAYASHI Takumi

  Japan Atomic Energy Agency, Naka

• SATOU Akira

  Japan Atomic Energy Agency, Tokai

• YONOMOTO Taisuke

  Japan Atomic Energy Agency, Tokai

• FEDERICI Gianfranco

  Fusion for Energy, c/o EFDA Garching and Max-Plank-Institut fuer Plasmaphysik

• OKANO Kunihiko

  The Graduate School of Science and Technology, Keio University

Abstract

Key aspects of the safety study of a water-cooled fusion DEMO reactor is reported. Safety requirements, dose target, DEMO plant model and confinement strategy of the safety study are briefly introduced. The internal hazard of a water-cooled DEMO, i.e. identification of hazardous inventories, identification of stored energies that can mobilize these hazardous inventories and identification of accident initiators and scenarios, are evaluated. It is pointed out that the enthalpy in the first wall/blanket cooling loops, the decay heat and the energy potentially released by the Be-steam chemical reaction are of special concern for the water-cooled DEMO. An ex-vessel loss-of-coolant accident (ex-VV LOCA) of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.

Journal

• Plasma and Fusion Research

  Plasma and Fusion Research 9 (0), 1405139-1405139, 2014

  The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

• water-cooled fusion DEMO
• safety study
• hazard analysis
• accident scenario analysis
• safety system

Details

• CRID: 1390001205253072512
• NII Article ID: 130005093288
• DOI: 10.1585/pfr.9.1405139
• ISSN: 18806821
• Web Site: https://www.jstage.jst.go.jp/article/pfr/9/0/9_1405139/_pdf
• Text Lang: en
• Data Source:
  • JaLC
  • Crossref
  • CiNii Articles
  • KAKEN
• Abstract License Flag: Disallowed