Developing and validating advanced divertor solutions on DIII-D for next-step fusion devices
Houyang Guo,D. N. Hill,A.W. Leonard,S.L. Allen,P.C. Stangeby,Daniel Thomas,Ezekial A Unterberg,Tyler Abrams,J.A. Boedo,A.R. Briesemeister,Dean A. Buchenauer,Igor Bykov,John Canik,C.P. Chrobak,Brent Covele,Rui Ding,R.P. Doerner,David Donovan,Huarong Du,D. Elder,David Eldon,Ane Lasa,M. Groth,Jerome Guterl,Aaro Järvinen,E.T. Hinson,Egemen Kolemen,C.J. Lasnier,Jeremy Lore,M. A. Makowski,Adam McLean,Brett H. Meyer,Auna Moser,Richard E. Nygren,Larry W Owen,T.W. Petrie,G.D. Porter,T.D. Rognlien,D.L. Rudakov,Chaofeng Sang,Cameron Samuell,H. Si,Oliver Schmitz,Aaron Sontag,Vlad Soukhanovskii,William R. Wampler,Huiqian Wang,J.G. Watkins +47 more
TL;DR: These efforts will lead to design, installation, and evaluation of an advanced divertor for DIII-D to enable highly dissipative divertor operation at core density, neutral fueling and impurity influx most compatible with high performance plasma scenarios and reactor relevant plasma facing components (PFCs).
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Abstract: A major challenge facing the design and operation of next-step high-power steady-state fusion devices is to develop a viable divertor solution with order-of-magnitude increases in power handling capability relative to present experience, while having acceptable divertor target plate erosion and being compatible with maintaining good core plasma confinement. A new initiative has been launched on DIII-D to develop the scientific basis for design, installation, and operation of an advanced divertor to evaluate boundary plasma solutions applicable to next step fusion experiments beyond ITER. Developing the scientific basis for fusion reactor divertor solutions must necessarily follow three lines of research, which we plan to pursue in DIII-D: (1) Advance scientific understanding and predictive capability through development and comparison between state-of-the art computational models and enhanced measurements using targeted parametric scans; (2) Develop and validate key divertor design concepts and codes through innovative variations in physical structure and magnetic geometry; (3) Assess candidate materials, determining the implications for core plasma operation and control, and develop mitigation techniques for any deleterious effects, incorporating development of plasma-material interaction models. These efforts will lead to design, installation, and evaluation of an advanced divertor for DIII-D to enable highly dissipative divertor operation at core density (nmore » e/n GW), neutral fueling and impurity influx most compatible with high performance plasma scenarios and reactor relevant plasma facing components (PFCs). In conclusion, this paper highlights the current progress and near-term strategies of boundary/PMI research on DIII-D.« less
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Citations
Physics of ultimate detachment of a tokamak divertor plasma
TL;DR: In this paper, the basic physics of the processes playing the most important role in divertor plasma detachment is reviewed, and the models used in the two-dimensional edge plasma transport codes that are widely used to address different issues of the edge plasma physics and to simulate the experimental data, as well as the numerical schemes and convergence issues, are described.
Magnetic diagnostics for magnetohydrodynamic instability research and the detection of locked modes in J-TEXT
TL;DR: The current status of the magnetic diagnostics dedicated to measuring magnetohydrodynamic (MHD) instabilities at the J-TEXT tokamak is described in this article.
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Radiative detached divertor with acceptable separatrix Zeff
TL;DR: In this article, a feasibility study is performed for the radiative detached divertor (RDD) concept, which characterizes a variety of detached plasmas with impurity amounts providing the highest levels of divertor radiation without X-point MARFE (XPM), based on a set of restrictive criteria for the leading plasma parameters (LPPs) including, e.g., tolerable peak power loads below 1MW/m2, low separatrix densities, allowable impurity concentrations, and acceptable Zeff values for a DIII-D like tokamak
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Simulations of divertor particle and heat loads in ohmic and L-mode plasmas in DIII-D, AUG, and JET using UEDGE
M Groth,G D Porter,M. E. Rensink,T. D. Rognlien,S. Wiesen,M. Wischmeier,T. Eich,A. Herrmann,S. Jachmich,C. J. Lasnier,H. W. Müller,J. G. Watkins,M. N. A. Beurskens,B. D. Bray,S. Brezinsek,N. H. Brooks,M E Fenstermacher,C Fuchs,A. Huber,A Kallenbach,A W Leonard,A. Meigs,D. L. Rudakov +22 more
- 17 May 2010
TL;DR: In this article, the UEDGE code of radiated power, and ion saturation currents and power loads to the target plates have been compared for density scans in ohmic and low confinement mode plasmas in DIII-D, ASDEX Upgrade, and JET.
Conceptual design of the island divertor coils on the J-TEXT tokamak
Song Zhou,Nengchao Wang,Bo Rao,Zhuo Huang,Da Li,Mao Li,Ruo Jia,Wei Zhang,Shiyi Peng,Zebao Song,Ying He,Kexun Yu,Yonghua Ding,Yunfeng Liang,Yunfeng Liang,Yunfeng Liang +15 more
TL;DR: In this paper, a set of new resonant magnetic perturbation (RMP) coils is designed for the J-TEXT tokamak to form the island divertor (ID) configuration.
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References
Geometrical properties of a “snowflake” divertor
TL;DR: In this article, a simple set of poloidal field coils is used to reach the situation in which the null of the poloidal magnetic field in the divertor region is of second order, not of first order as in the usual X-point divertor.
Finalizing the ITER divertor design: The key role of SOLPS modeling
TL;DR: A review of the development of edge plasma modeling at ITER and of its interaction with the evolving divertor design is presented in this article, where the SOLPS (B2-Eirene) code has been developed for, and applied to, the evaluation and the design of the ITER divertor for the last 15 years.
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Effects of divertor geometry on tokamak plasmas
TL;DR: The design, construction and operation of advanced divertors have been the main topics of tokamak research during the last decade as discussed by the authors, and the design of these divertors has been optimized to provide: a large operating density range for partially detached plasmas with large radiative losses; satisfactory particle control by efficient deuterium pumping; and He exhaust capability sufficient to remove fusion ashes when extrapolated to next step devices.
182
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade
R. Dux,V. Bobkov,A. Herrmann,A. Janzer,A. Kallenbach,Rudolf Neu,M. Mayer,H. W. Müller,R. Pugno,Th. Pütterich,V. Rohde,A. C. C. Sips +11 more
TL;DR: ASDEX Upgrade has successfully started the second experimental campaign with a full tungsten coverage of the plasma facing components and without using a boronisation for machine conditioning as discussed by the authors.
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Compact DEMO, SlimCS: design progress and issues
Kenji Tobita,S. Nishio,Mikio Enoeda,Hisato Kawashima,G. Kurita,Hiroyasu Tanigawa,Hideo Nakamura,Mitsuru Honda,A. Saito,Satoshi Sato,Takumi Hayashi,Nobuyuki Asakura,S. Sakurai,Takeo Nishitani,Takahisa Ozeki,M. Ando,Koichiro Ezato,Kiyotaka Hamamatsu,Takanori Hirose,Tsuyoshi Hoshino,Shunsuke Ide,Takashi Inoue,Takaaki Isono,C. Liu,Satoshi Kakudate,Yoshinori Kawamura,Mori Seiji,Masaru Nakamichi,Hiroshi Nishi,Takashi Nozawa,Kentaro Ochiai,H. Ogiwara,Naoyuki Oyama,Keishi Sakamoto,Yoshiteru Sakamoto,Yohji Seki,Yusuke Shibama,Katsuhiro Shimizu,Sadaaki Suzuki,Koji Takahashi,Daigo Tsuru,Toshihiko Yamanishi,T. Yoshida +42 more
TL;DR: In this article, the design progress in a compact low aspect ratio (low A) DEMO reactor, "SlimCS", and its design issues are reported The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme.
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