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Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC

文献类型：期刊论文

作者Liu, Li1; Guo, Yong2; Chan, Vincent1; Mao, Shifeng1; Wang, Yifeng1; Pan, Chengkang2; Luo, Zhengping2; Zhao, Hailin2; Ye, Minyou1
刊名NUCLEAR FUSION
出版日期2017-06-01
卷号57期号:6页码:1-14
关键词Transport Models Tokamak Ramp Up Tokamak Simulation Code (Tsc)
DOI10.1088/1741-4326/aa6b7f
文献子类Article
英文摘要The confidence in ramp up scenario design of the China fusion engineering test reactor (CFETR) can be significantly enhanced using validated transport models to predict the current profile and temperature profile. In the tokamak simulation code (TSC), two semi-empirical energy transport models (the Coppi-Tang (CT) and BGB model) and three theory-based models (the GLF23, MMM95 and CDBM model) are investigated on the CFETR relevant ramp up discharges, including three DIII-D ITER-like ramp up discharges and one EAST ohmic discharge. For the DIII-D discharges, all the transport models yield dynamic l(i) within +/- 0.15 deviations except for some time points where the experimental fluctuation is very strong. All the models agree with the experimental beta(p) except that the CT model strongly overestimates beta p in the first half of ramp up phase. When applying the CT, CDBM and GLF23 model to estimate the internal flux, they show maximum deviations of more than 10% because of inaccuracies in the temperature profile predictions, while the BGB model performs best on the internal flux. Although all the models fall short in reproducing the dynamic l(i) evolution for the EAST tokamak, the result of the BGB model is the closest to the experimental l(i). Based on these comparisons, we conclude that the BGB model is the most consistent among these models for simulating CFETR ohmic ramp-up. The CT model with improvement for better simulation of the temperature profiles in the first half of ramp up phase will also be attractive. For the MMM95, GLF23 and CDBM model, better prediction of the edge temperature will improve the confidence for CFETR L-mode simulation. Conclusive validation of any transport model will require extensive future investigation covering a larger variety discharges.
WOS关键词NEOCLASSICAL CONDUCTIVITY ; D TOKAMAK ; PLASMA ; ITER ; DISCHARGES ; SIMULATION ; BARRIER ; DESIGN
WOS研究方向Physics
语种英语
WOS记录号WOS:000400923400003
资助机构National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Magnetic Confinement Fusion Research Program of China(2014GB110000 ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; National Natural Science Foundation of China(11305216) ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB110003 ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000) ; 2014GB103000)
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/31862]  
专题合肥物质科学研究院_中科院等离子体物理研究所
作者单位1.Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230026, Peoples R China
2.Chinese Acad Sci, Inst Plasma Phys, 350 Shushanhu Rd, Hefei, Peoples R China
推荐引用方式
GB/T 7714		 Liu, Li,Guo, Yong,Chan, Vincent,et al. Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC[J]. NUCLEAR FUSION,2017,57(6):1-14.
APA Liu, Li.,Guo, Yong.,Chan, Vincent.,Mao, Shifeng.,Wang, Yifeng.,...&Ye, Minyou.(2017).Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC.NUCLEAR FUSION,57(6),1-14.
MLA Liu, Li,et al."Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC".NUCLEAR FUSION 57.6(2017):1-14.

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来源：合肥物质科学研究院

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