論文

査読有り
2021年3月

Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design

Nuclear Materials and Energy
  • Asakura N
  • ,
  • Hoshino K
  • ,
  • Homma Y
  • ,
  • Sakamoto Y

26
記述言語
英語
掲載種別
研究論文(学術雑誌)
DOI
10.1016/j.nme.2020.100864
出版者・発行元
Nuclear Materials and Energy

© 2020 The Author(s) Handling of a large thermal power exhausted from the confined plasma is one of the most important issues for ITER and DEMO. A conventional divertor, which has the closed geometry similar to that of ITER and longer leg of 1.6 m, was proposed for the Japanese (JA) DEMO reactor (Rp/ap = 8.5/2.42 m). A radiative cooling scenario of Ar impurity seeding and the divertor performance have been demonstrated by SONIC simulation, in order to evaluate the power exhaust in JA-DEMO 2014 (primary design with Psep ~ 283 MW) and JA-DEMO with higher plasma elongation (a revised design with Psep ~ 235 MW). The divertor operation with the peak qtarget ≤ 10 MWm−2 was determined in the low nesep of 2–3 × 1019 m−3 under the severe conditions of reducing radiation loss fraction, i.e. f*raddiv = (Pradsol + Praddiv)/Psep, and diffusion coefficients (χ and D). The divertor geometry and reference key parameters (f*raddiv ~ 0.8, χ = 1 m2/s and D = 0.3 m2/s) were so far consistent with the power exhaust concepts in the nesep range, and the revised JA-DEMO design has advantages of wider nesep range and enough margin for the divertor operation. For either severe assumption of f*raddiv ~ 0.7 or χ and D to the half value, higher nesep operation was required for the primary design in order to control the peak qtarget ≤ 10 MWm−2, i.e. the operation window was reduced. Applying the two severe assumptions, the divertor operation was difficult in the low nesep range for the both designs.

リンク情報
DOI
https://doi.org/10.1016/j.nme.2020.100864
URL
https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=85097716960&origin=inward
ID情報
  • DOI : 10.1016/j.nme.2020.100864

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