TY - JOUR
T1 - Physics design study of the divertor power handling in 8 m class DEMO reactor
AU - Joint Special Design Team for Fusion DEMO
AU - Hoshino, Kazuo
AU - Asakura, Nobuyuki
AU - Tokunaga, Shinsuke
AU - Homma, Yuki
AU - Shimizu, Katsuhiro
AU - Sakamoto, Yoshiteru
AU - Tobita, Kenji
N1 - Funding Information:
SONIC simulations were carried out using the HELIOS supercomputer system at International Fusion Energy Research Centre (IFERC), Aomori, Japan, under the Broader Approach (BA) collaboration between Euratom and Japan, implemented by Fusion for Energy and Japan Atomic Energy Agency. This work is mainly carried out within the framework of the DEMO Design Activity under the BA-IFERC project, and partially supported by Grant-in-Aid for Young Scientists (B) and Grant-in-Aid for Scientific Research (B) of Japan Society for the Promotion of Science.
Publisher Copyright:
© 2017 Elsevier B.V.
PY - 2017/11
Y1 - 2017/11
N2 - The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with the fusion power of 1.5 GW. Due to the high impurity radiation power (80% of the exhausted power), the full detachment at the inner target and the partial detachment at the outer target are obtained for a relatively low electron density of 1.8 × 1019 m−3 at the outer mid-plane separatrix. The SONIC simulation shows the target heat load less than 8 MW/m2, which can be handled by the ITER-like divertor target, for both target. However, at the outer target, the ion temperature is still high which may cause the target erosion. For the divertor power handling and suppression of the target erosion, the divertor design study have to be further proceeded as well as the core plasma design. Dependence of the mid-plane separatrix density and the impurity concentration on the fuel gas puff is also studied. With increasing fuel gas puff rate, the mid-plane separatrix density increases and the Ar impurity concentration at the outer mid-plane decreases to 0.5%.
AB - The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with the fusion power of 1.5 GW. Due to the high impurity radiation power (80% of the exhausted power), the full detachment at the inner target and the partial detachment at the outer target are obtained for a relatively low electron density of 1.8 × 1019 m−3 at the outer mid-plane separatrix. The SONIC simulation shows the target heat load less than 8 MW/m2, which can be handled by the ITER-like divertor target, for both target. However, at the outer target, the ion temperature is still high which may cause the target erosion. For the divertor power handling and suppression of the target erosion, the divertor design study have to be further proceeded as well as the core plasma design. Dependence of the mid-plane separatrix density and the impurity concentration on the fuel gas puff is also studied. With increasing fuel gas puff rate, the mid-plane separatrix density increases and the Ar impurity concentration at the outer mid-plane decreases to 0.5%.
KW - DEMO reactor
KW - Divertor plasma design
KW - Power handling
KW - Radiative cooling
KW - SONIC
UR - http://www.scopus.com/inward/record.url?scp=85017353650&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85017353650&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2017.03.068
DO - 10.1016/j.fusengdes.2017.03.068
M3 - Article
AN - SCOPUS:85017353650
SN - 0920-3796
VL - 124
SP - 352
EP - 355
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
ER -