Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design
Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design
复制标题
日本DEMO设计偏滤器脱离和临界功率排气参数的模拟研究
DOI:
10.1016/j.nme.2020.100864
复制
发表时间:
2021
影响因子:
2.6
通讯作者:
Joint Special Design Team for Fusion Demo
中科院分区:
文献类型:
--
作者:
N. Asakura;K. Hoshino;Y. Homma;Y. Sakamoto;Joint Special Design Team for Fusion Demo
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 withPsep~ 283 MW) and JA-DEMO with higher plasma elongation (a revised design withPsep~ 235 MW). The divertor operation with the peakqtarget≤ 10 MWm−2was determined in the lownesepof 2–3 × 1019m−3under the severe conditions of reducing radiation loss fraction, i.e.f*raddiv= (Pradsol+Praddiv)/Psep, and diffusion coefficients (χandD). The divertor geometry and reference key parameters (f*raddiv~ 0.8,χ= 1 m2/s andD= 0.3 m2/s) were so far consistent with the power exhaust concepts in theneseprange, and the revised JA-DEMO design has advantages of widerneseprange and enough margin for the divertor operation. For either severe assumption off*raddiv~ 0.7 orχandDto the half value, highernesepoperation was required for the primary design in order to control the peakqtarget≤ 10 MWm−2, i.e. the operation window was reduced. Applying the two severe assumptions, the divertor operation was difficult in the lowneseprange for the both designs.