Journal ArticleDOI
Physics basis and design of the ITER plasma-facing components
R.A. Pitts,S. Carpentier,Frederic Escourbiac,T. Hirai,V. Komarov,A.S. Kukushkin,S.W. Lisgo,A. Loarte,Mario Merola,R. Mitteau,A.R. Raffray,Michiya Shimada,P.C. Stangeby +12 more
TLDR
The ITER PFC design has now reached a rather mature stage following the 2007 ITER Design Review as discussed by the authors, and the key elements of the design, reviews the physics drivers, essentially thermal load specifications, which have defined the concept and discusses a selection of material and design issues.About:
This article is published in Journal of Nuclear Materials.The article was published on 2011-08-01. It has received 368 citations till now. The article focuses on the topics: Divertor.read more
Citations
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Plasma-Facing Components in Tokamaks : Material Modification and Fuel Retention
TL;DR: In this article, a set of stainless steel (SS) and molybdenum mirror samples located in the divertor and at the outer midplane of the vessel were exposed in JET from 2005 to 2007.
Journal ArticleDOI
Beryllium erosion and redeposition in ITER H, He and D–T discharges
TL;DR: The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber as mentioned in this paper .
Verification and validation procedures with applications to plasma-edge turbulence simulations
TL;DR: Developing and applying rigorous verification and validation procedures to plasma turbulence simulations and investigating the impact of the shape of magnetic equilibrium on SOL turbulence is targeted to increase the reliability of the SOL modeling.
Journal ArticleDOI
Characterization of thermomechanical damage on tungsten surfaces during long-duration plasma transients
TL;DR: The High Energy Flux Test Facility (HEFTY) as discussed by the authors is equipped with a Praxair model SG-100 plasma gun, which is nominally rated at 80kW of continuous operation, of which approximately 30kW reaches the target due to thermal losses.
Journal ArticleDOI
Performance of straight tungsten mono-block test mock-ups using new high heat flux test facility at IPR
Yashashri Patil,S.S. Khirwadkar,Sunil Belsare,Rajamannar Swamy,M. S. Khan,Sudhir Tripathi,Kedar Bhope,D. Krishnan,Prakash Mokaria,Nikunj Patel,I. Antwala,K. Galodiya,Mayur Mehta,Tushar Patel +13 more
TL;DR: In this paper, the authors describe the newly established high heat flux test facility (HHFTF) at IPR in India, which is used to simulate typical steady state and transient thermal load conditions for testing Divertor plasma facing components using a 200kW Electron Beam as heat source.
References
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Journal ArticleDOI
Recent analysis of key plasma wall interactions issues for ITER
J. Roth,E. Tsitrone,A. Loarte,Th. Loarer,G.F. Counsell,Rudolf Neu,V. Philipps,S. Brezinsek,Michael Lehnen,P. Coad,Ch. Grisolia,Klaus Schmid,K. Krieger,A. Kallenbach,Bruce Lipschultz,R.P. Doerner,Rion A. Causey,V.K. Alimov,W. M. Shu,O. V. Ogorodnikova,A. Kirschner,Gianfranco Federici,A.S. Kukushkin +22 more
TL;DR: In this paper, different aspects of the PWI are assessed in their importance for the initial wall materials choice: CFC for the strike point tiles, W in the divertor and baffle and Be on the first wall.
Journal ArticleDOI
Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER
A. Loarte,G. Saibene,R. Sartori,David Campbell,M. Becoulet,L. D. Horton,T. Eich,Albrecht Herrmann,G. Matthews,Nobuyuki Asakura,A. V. Chankin,Anthony Leonard,G. Porter,G. Federici,G. Janeschitz,Michiya Shimada,M. Sugihara +16 more
TL;DR: In this paper, the authors show that ELM energy losses are correlated with the density and temperature of the pedestal plasma before the ELM crash and the timescale of ELM particle fluxes.
Journal ArticleDOI
Transport-driven Scrape-Off-Layer flows and the boundary conditions imposed at the magnetic separatrix in a tokamak plasma
Brian LaBombard,J. E. Rice,Amanda Hubbard,J. W. Hughes,Martin Greenwald,J. H. Irby,Yuxuan Lin,Bruce Lipschultz,E.S. Marmar,C.S. Pitcher,N. Smick,S.M. Wolfe,S.J. Wukitch +12 more
TL;DR: In this paper, topology-dependent flow boundary conditions on the confined plasma were investigated in the low and high-field side scrape-off-layer (SOL) regions in Alcator C-Mod.
Journal ArticleDOI
Fluctuations and transport in the TCV scrape-off layer
Odd Erik Garcia,J. Horacek,R.A. Pitts,Anders Nielsen,Wojciech Fundamenski,Volker Naulin,J. Juul Rasmussen +6 more
TL;DR: In this article, the authors investigated the particle and radial flux density statistics in the scrape-off layer of TCV plasmas and direct comparison with two-dimensional interchange turbulence simulations at the outer midplane.
Journal ArticleDOI
Status and physics basis of the ITER divertor
R.A. Pitts,A.S. Kukushkin,A. Loarte,A. Martin,Mario Merola,C.E. Kessel,V. Komarov,Michiya Shimada +7 more
TL;DR: The ITER divertor design is the culmination of years of physics and engineering effort, building confidence that this critical component will satisfy the requirements and meet the challenge of burning plasma operation as discussed by the authors.
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