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Abstract

This paper summarizes the evolution of Japanese DEMO design studies in a retrospective manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently working on the conceptual study of a steady state DEMO (JA DEMO) with a major radius of 8.5 m and fusion power of 1.5-2 GW based on water-cooled solid breeding (WCSB) blanket with PWR water condition (290-325ºC, 15.5 MPa). Such a lower Pfus allows to find realistic design solutions for divertor heat removal. Recognizing that divertor heat removal is one of the most challenging issues on DEMO, divertor design has been carried out in different approaches including numerical divertor plasma simulation, magnetic configurations, heat sink design, etc. It is noteworthy that the latest divertor simulation led to a design window allowing divertor heat removal of the peak heat flux of < 10 MW/m2. Breeding blanket (BB) design has been concentrated on simplification of the internal structure and pressure tightness of BB casing against in-box LOCA (Loss Of Coolant Accident). Due to a large amount of radioactive waste generated in periodic replacement of in-vessel components, downsizing of waste-related facilities came to be regarded as a significant design issue. A possible waste management for reducing temporary waste storage was proposed and its impact on the plant layout was assessed.

Journal

  • Fusion Science and Technology

    Fusion Science and Technology (75), 372-383, 2019-06

    Taylor and Francis

Codes

  • NII Article ID (NAID)
    120006712769
  • Text Lang
    ENG
  • Article Type
    journal article
  • ISSN
    1536-1055
  • Data Source
    IR 
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