Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling
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In this paper, a detailed study of the parameter space of the ITER divertor with the B2-Eirene code is presented, where relations between plasma parameters at the separatrix, the interface between the core and edge plasma, are parametrized to provide a set of boundary conditions for the core models.Abstract:
Results of a detailed study of the parameter space of the ITER divertor with the B2-Eirene code are presented. Relations between plasma parameters at the separatrix, the interface between the core and edge plasma, are parametrized to provide a set of boundary conditions for the core models. The reference ITER divertor geometry is compared with the straight target option, and the possibility of controlling the edge density by shifting the plasma equilibrium in ITER is explored.read more
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Chapter 4: Power and particle control
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TL;DR: In this paper, the authors describe the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER and compare their predictions with the new experimental results.
Journal ArticleDOI
Chapter 2: Plasma confinement and transport
E. J. Doyle,Wayne A Houlberg,Yutaka Kamada,V. S. Mukhovatov,T.H. Osborne,A. R. Polevoi,G. Bateman,J. W. Connor,J. G. Cordey,T. Fujita,Xavier Garbet,T. S. Hahm,L. D. Horton,A. E. Hubbard,F. Imbeaux,Frank Jenko,J. E. Kinsey,Yasuaki Kishimoto,J.X. Li,T. C. Luce,Y. R. Martin,M. Ossipenko,V.V. Parail,A. G. Peeters,T. L. Rhodes,J. E. Rice,C. M. Roach,V. A. Rozhansky,F. Ryter,G. Saibene,R. Sartori,A. C. C. Sips,J. A. Snipes,M. Sugihara,E. J. Synakowski,H. Takenaga,Tomonori Takizuka,K. Thomsen,M. R. Wade,H. R. Wilson,Itpa Confinement Database,Itpa Pedestal +41 more
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The EIRENE and B2-EIRENE Codes
TL;DR: The EIRENE neutral gas transport Monte Carlo code has been developed initially for TEXTOR applications and can be used to solve more general linear kinetic transport equations by applying a stochastic rather than a numerical or analytical method of solution.
Journal ArticleDOI
Physics basis for the first ITER tungsten divertor
R.A. Pitts,Xavier Bonnin,Frederic Escourbiac,H. Frerichs,James Paul Gunn,T. Hirai,A.S. Kukushkin,A.S. Kukushkin,E. G. Kaveeva,M.A. Miller,David Moulton,V. A. Rozhansky,I. Senichenkov,E. Sytova,E. Sytova,E. Sytova,Oliver Schmitz,P.C. Stangeby,G. De Temmerman,I. Veselova,S. Wiesen +20 more
TL;DR: In this paper, the main focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SolPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne).
Journal ArticleDOI
Finalizing the ITER divertor design: The key role of SOLPS modeling
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References
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Chapter 1: Overview and summary
TL;DR: The ITER Physics Basis as mentioned in this paper presents and evaluates the physics rules and methodologies for plasma performance projections, which provide the basis for the design of a tokamak burning plasma device whose goal is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.
Journal ArticleDOI
B2-EIRENE simulation of ASDEX and ASDEX-Upgrade scrape-off layer plasmas
Ralf Schneider,Detlev Reiter,HP Zehrfeld,Bastiaan J. Braams,Martine Baelmans,J Geiger,H. Kastelewicz,J. Neuhauser,R. Wunderlich +8 more
TL;DR: In this paper, the 2D multifluid edge code B2 coupled with the 3D neutral gas Monte Carlo code EIRENE is used for edge interpretation and model validation on the axisymmetric poloidal divertor experiments ASDEX and ASDEX-Upgrade.
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Burn condition, helium particle confinement and exhaust efficiency*
Detlev Reiter,G.H. Wolf,H. Kever +2 more
TL;DR: In this article, the burn condition for D-T plasmas is derived in a form which accounts for the stationary helium concentration determined by the coupling of the fusion power and helium production.
Journal ArticleDOI
Divertor modelling and extrapolation to reactor conditions
A S Kukushkin,H.D. Pacher +1 more
TL;DR: In this article, the authors summarized the results of divertor modelling and incorporated them in the ITER-FEAT divertor design, such as the beneficial effect of V-shaped targets, the importance of high gas conductivity between the divertors, and the role of deep core fuelling in maintaining the plasma density.
Journal ArticleDOI
ELM energy scaling in DIII-D
A.W. Leonard,R. J. Groebner,M.A. Mahdavi,T.H. Osborne,M.E. Fenstermacher,C.J. Lasnier,T.W. Petrie +6 more
TL;DR: In this paper, the energy lost from the pedestal region due to an average ELM in DIII-D is determined from changes to the electron density and temperature profiles as measured by Thomson scattering.
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