[논문]Recent progress in the design of the K-DEMO divertor

Kwon, Sungjin; Im, Kihak; Hong, Suk-Ho; Lee, Hyungho; Rognlien, Thomas D.; Meyer, William; Kim, Keeman

doi:10.1016/j.fusengdes.2020.111770

[해외논문] Recent progress in the design of the K-DEMO divertor 원문보기

Fusion engineering and design, v.159, 2020년, pp.111770 -

Kwon, Sungjin (National Fusion Research Institute) , Im, Kihak (National Fusion Research Institute) , Hong, Suk-Ho (National Fusion Research Institute) , Lee, Hyungho (National Fusion Research Institute) , Rognlien, Thomas D. (Lawrence Livermore National Laboratory) , Meyer, William (Lawrence Livermore National Laboratory) , Kim, Keeman (National Fusion Research Institute)

Abstract ▼ AI-Helper

Abstract The preliminary conceptual design of the Korean fusion demonstration reactor (K-DEMO) with a major radius of 6.8 m and the fusion power of 2200 MW has been studied since 2012. The overall configuration of the K-DEMO divetor system based on the ITER-like water-cooled tungsten technology is a double-null type symmetric divertor subdivided into 32 toroidal modules for the vertical maintenance. A detached divertor scenario with impurity seeding was considered as the primary approach for the power exhaust to reduce the peak heat flux lower than the engineering limit of 10 MW/m2. The power exhaust performance at the scrap off layer was estimated by using UEDGE-2D code, a two-dimensional fluid transport code for collisional edge plasma and neutral species like N, Ne, and Ar. Particle and heat flux on inboard and outboard divertor targets were calculated for the detached cased depending on parameters such as the impurity seeding rate, pumping rate, and the pedestal density. On the other hand, a magnetic solution like X-divertor, snowflake divertor, and super X-divertor to expand the plasma wet area was considered for K-DEMO since the detached divertor increasing a radiation fraction by impurity seeding might be able to be unstable. However, the extremely high current of poloidal coils was required more than the engineering limit, 20 MA, to form magnetic field lines for the alternative divertors. Based on the physical calculation of the edge plasma, engineering analyses were carried out to find out the thermal and structural reliability. The thermo-hydraulic analysis confirmed thermal stability, whether all comprising materials are operating within their allowable temperature windows when the case of the peak heat flux is set to 10 MW/m2 on the outboard divertor target. The response surface optimization method derived two optimal design candidates employing two kinds of heat sink materials, respectively: the reduced activation ferritic martensitic (RAFM) steel and CuCrZr alloy. The drawbacks and merits of the two materials were definite. The optimal design with applying RAFM steel was vulnerable to withstand thermal and mechanical loads since low thermal conductivity caused too thin thickness of the heat sink. On the other hand, the CuCrZr alloy has critical drawbacks in terms of activation and radioactive waste despite its high thermal conductivity. Meanwhile, preliminary electromagnetic (EM) analysis was carried out to estimate the EM loads caused by the abnormal behaviors of plasma since EM loads are one of the most critical external loads for designing a DEMO divertor. Highlights A water-cooled tungsten monoblock divertor concept has been considered in the K-DEMO. The detached divertor study has been carried out by the impurity seeding for N, Ne, and Ar to reduce the peak heat flux and particle flux. The optimum designs were derived by the response surfaces optimization method for CuCrZr and RAFM steel, the major candidates for the heat sink in the K-DEMO. The alternative divertor concepts were studied for the super X-divertor and snowflake divertor.

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DOI : 10.1016/j.fusengdes.2020.111770
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