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Modeling and Analysis of the W7-X High Heat-Flux Divertor Scraper Element
Arnold Lumsdaine;Jean Boscary;Emily Clark;Kivanc Ekici;Jeffrey Harris;Dean McGinnis;Jeremy D. Lore;Alan Peacock;Joseph Tipton;Jrg Tretter
The Wendelstein 7-X stellarator experiment is scheduled for the completion of device commissioning and the start of first plasma in 2015. At the completion of the first two operational phases, the inertially cooled test divertor unit will be replaced with an actively cooled high heat-flux divertor, which will enable the device to increase its pulse length to steady-state plasma performance. Plasma...Show More
Design and Analysis of Divertor Scraper Elements for the W7-X Stellarator
Jeremy D. Lore;Tamara Andreeva;Jean Boscary;Sergey Bozhenkov;Joachim Geiger;Jeffrey H. Harris;Hauke Hoelbe;Arnold Lumsdaine;Dean McGinnis;Alan Peacock;Joseph Tipton
A set of new water-cooled divertor components is being designed for the Wendelstein 7-X stellarator to protect the edges of the primary plasma facing components during the bootstrap current evolution (~ 40 s). These new components, referred to as scraper elements (SEs), will intercept field lines and associated heat flux that would otherwise overload the main target edges in certain operational sc...Show More
Status of High Heat Flux Components at W7-X
Alan Peacock;Jean Boscary;Michael Czerwinski;Gunnar Ehrke;Henri Greuner;Patrick Junghanns;Boris Mendelevitch;Michael Smirnow;Reinhold Stadler;Harald Tittes;Jörg Tretter
The actively water-cooled in-vessel components (IVCs) of the stellarator Wendelstein 7-X consist of the divertor, the first wall protection components, the port liners, each designed for different loading conditions, and the associated pipework, the control coils, the cryo-pump system, the Glow discharge electrodes, and a set of diagnostics. The divertor, designed for high heat fluxes (HHFs), is a...Show More
Summary of Research and Development Activities for the Production of the Divertor Target Elements of Wendelstein 7-X
The realization of the high heat flux divertor of the stellarator Wendelstein 7-X requires the production of 890 target elements. Since the divertor has to operate for 30 min with an input continuous wave (cw) plasma power of 10 MW, the target elements need to be actively water cooled. A target element is made of a CuCrZr copper alloy heat sink armored with carbon fiber reinforced carbon (CFC) NB3...Show More
Configuration Space Control Using the Example of In-Vessel Components for Wendelstein 7-X
Jörg Tretter;Jean Boscary;Boris Mendelevitch;Alan Peacock;Reinhold Stadler
Concurrent engineering with the design of increasingly complex components requires additional tools to avoid space conflicts. Configuration space control is a key technology necessary to achieve the required design efficiency and product development of a complex experiment. Easily accessible solutions available within CAD frameworks, product data management, and configuration management systems cu...Show More
Physics and engineering design of the divertor scraper element for the W7-X stellarator
J. D. Lore;T. Andreeva;J. Boscary;S. Bozhenkov;J. Geiger;J. H. Harris;H. Hoelbe;A. Lumsdaine;D. McGinnis;A. Peacock;J. Tipton
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
Year: 2013 | Conference Paper |
Cited by: Papers (1)
A new high-heat-flux divertor component for the Wendelstein 7-X (W7-X) stellarator, the scraper element (SE), is being designed to protect overloaded areas of the primary divertor module during the bootstrap current evolution in certain operational scenarios. The SE will be constructed from water-cooled carbon fiber reinforced composite monoblocks capable of handling a steady-state heat load of 20...Show More
Wendelstein 7-X high heat flux components
A. Peacock;J. Boscary;M. Czerwinski;G. Ehrke;H. Greuner;P. Junghanns;B. Mendelevitch;M. Smirnow;R. Stadler;H. Tittes;J. Tretter
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
Year: 2013 | Conference Paper |
Cited by: Papers (6)
The actively water-cooled In-Vessel Components (IVCs) of the stellarator Wendelstein 7-X consist of the divertor, the first wall protection components, the port liners, each designed for different loading conditions, and the associated pipework, the control coils, the cryo-pump system, the Glow discharge electrodes, and a set of diagnostics. The divertor, designed for high heat fluxes, is a set of...Show More
Configuration space control of in-vessel components for Wendelstein 7-X
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
Year: 2013 | Conference Paper |
Cited by: Papers (4)
Concurrent engineering with the design of increasingly complex components requires addition tools to avoid space conflicts. Configuration Space Control is a key technology necessary to achieve the required design efficiency and product development of a complex experiment. Easily accessible solutions available within CAD Frameworks, Product Data Management, and Configuration Management Systems curr...Show More
Wendelstein 7-X high heat-flux divertor scraper element
A. Lumsdaine;J. Boscary;E. Clark;K. Ekici;J. Harris;D. McGinnis;J. D. Lore;A. Peacock;J. Tretter
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
Year: 2013 | Conference Paper |
Cited by: Papers (2)
The Wendelstein 7-X stellarator experiment is scheduled to complete construction in 2014 and begin operation in 2015. After the first operational phase, the inertially cooled test divertor unit will be replaced with an actively cooled high heat-flux divertor which will enable the device to increase its pulse length and its steady-state plasma performance. Plasma simulations show that the evolution...Show More
Development activities for the target elements of the Wendelstein 7-X divertor
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
Year: 2013 | Conference Paper |
Cited by: Papers (1)
The 19.6 m2 high heat flux loaded area of the divertor of the stellarator Wendelstein 7-X (W7-X), which follows the twisted plasma shape, consists of 890 individual actively cooled target elements. A target element is made of a water-cooled CuCrZr copper alloy heat sink armored with CFC NB31 tiles and is specified to withstand a stationary heat flux of 10 MW/m2 on its main area and 5 MW/m2 at the ...Show More
A proposed scraper element to protect the end of the W7-X divertor target elements
A. Peacock;J. Kißlinger;J. Boscary;J. Geiger;F. Hurd;R. König;M. Krychowiak;R. Stadler;M. Smirnow;J. Tretter;A. Werner
2011 IEEE/NPSS 24th Symposium on Fusion Engineering
Year: 2011 | Conference Paper |
Cited by: Papers (5)
The three main areas of the W7-X divertor target are: the horizontal target, the vertical target and the high iota tail, with a pumping gap between the horizontal and vertical targets. For each of the standard operational scenarios the target has been designed so that, based on vacuum field calculations, the plasma strike points lie away from the ends of the target. Each target consists of CFC arm...Show More
Radiological properties of tritiated dusts and flakes from the JET tokamak
18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050)
Year: 1999 | Conference Paper |
Cited by: Papers (1)
Operation of JET with a C/Be first wall has generated significant amounts of dust and deposit through plasma erosion processes and Be evaporation. The introduction of tritium in the Deuterium-Tritium Experiment (DTE1) under the Mk IIa divertor configuration has further resulted in deposits of tritiated flakes with specific activities in excess of 1 TBq/gram. The retention of large quantities of tr...Show More
The JET programme on the development of beryllium clad components for ITER
C. Ibbott;D. Ciric;E. Deksnis;H. Falter;A. Peacock;M. Watson
Proceedings of 16th International Symposium on Fusion Engineering
Year: 1995 | Conference Paper |
JET under a contract with the European Home Team and in co-operation with industry, is carrying out a programme to support development of beryllium (Be) divertor components for ITER. The basis for this programme is the existing experience on the brazing of thin (1.5 to 3 mm) Be cladding to CuCrZr hypervapotrons using a silver based alloy (Incusil ABA), which demonstrated critical heat fluxes of up...Show More
The use of carbon fibre composites in divertor target plate tiles and structures
H. Altmann;E. Deksnis;J. Fanthome;C. Froger;C. Lowry;A. Peacock;M.A. Pick
Proceedings of 16th International Symposium on Fusion Engineering
Year: 1995 | Conference Paper |
Cited by: Papers (1)
Carbon-carbon fibre composite (CFC), in the form of target plate tiles, is a standard material for intercepting conducted power in divertors. Its good thermal conductivity and ability to withstand high temperatures without melting give it an advantage over other materials for plasma facing components. Supporting structures are generally made from stainless steels or Inconels. In a radiating divert...Show More
The new first wall configuration of JET
M.A. Pick;H. Altmann;P. Andrew;G. Celentano;C. Froger;J. Graham;F. Hurd;G. Israel;P. Lomas;B. Macklin;E. Martin;R. Middleton;P. Miele;R. Mohanti;P. Noll;W.J. Parsons;A.T. Peacock;L. Rossi;C. Sborchia;S.M. Scott;J. Tait
The installation of the pumped divertor into the JET machine during 1992-1993 includes a total refurbishing of most of the in-vessel components and a new first wall configuration. The paper describes the new components, and the requirements which were implemented in the design. These include the requirements related to normal plasma operation and off-normal effects such as disruptions as well as t...Show More
Development of beryllium-carbide fibre reinforced beryllium for fusion applications
15th IEEE/NPSS Symposium on Fusion Engineering - Supplement,
Year: 1993 | Conference Paper |
Cited by: Patents (1)
Be-Be/sub 2/C composite materials have been produced via two routes. The first produces a two dimensional composite with woven carbon cloth converted to the Be/sub 2/C fibres and infiltrated with molten Be with the assistance of a wetting agent. A number of wetting agents with low atomic number were tried, the best being silicon, either in metallic form or as polydimethylsiloxane. The second compo...Show More
The new first wall configuration of JET
M.A. Pick;H. Altmann;P. Andrew;G. Celentano;C. Froger;J. Graham;F. Hurd;G. Israel;P. Lomas;B. Macklin;E. Martin;R. Middleton;P. Miele;R. Mohanti;P. Noll;W.J. Parsons;A.T. Peacock;L. Rossi;C. Sborchia;S.M. Scott;J. Tait
15th IEEE/NPSS Symposium on Fusion Engineering - Supplement,
Year: 1993 | Conference Paper |
Cited by: Papers (4)
The installation of the pumped divertor into the JET machine during 1992-1993 includes a total refurbishing of most of the in-vessel components and a new first wall configuration. The paper describes the new components, and the requirements which were implemented in the design. These include the requirements related to normal plasma operation and off-normal effects such as disruptions as well as t...Show More
Design of the JET pumped divertor
M. Huguet;H. Altmann;P. Barabaschi;E. Bertolini;K. Dietz;E. Deksnis;H. Falter;C. Froger;M. Garribba;A. Kaye;J.R. Last;R. Lobel;E. Martin;P. Massmann;P. Noll;W. Obert;S. Papastergiou;A. Peacock;M. Pick;P.H. Rebut;L. Rossi;C. Sborchia;G. Sannazzaro;A. Tesini;R. Tivey
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering
Year: 1991 | Conference Paper |
Cited by: Papers (2)
The JET (Joint European Torus) pumped divertor aims at demonstrating an effective method of impurity control with quasi-stationary plasmas of thermonuclear grade in a next step relevant, axisymmetric configuration. The magnetic configuration is produced by a set of four coils internal to the JET vacuum vessel. These coils can produce a range of configurations and also sweep the magnetic field line...Show More
Design of the JET pumped divertor
M. Huguet;H. Altmann;P. Barabaschi;E. Bertolini;K. Dietz;E. Deksnis;H. Falter;C. Froger;M. Garribba;A. Kaye;J.R. Last;R. Lobel;E. Martin;P. Massmann;P. Noll;W. Obert;S. Papastergiou;A. Peacock;M. Pick;P.H. Rebut;L. Rossi;C. Sborchia;G. Sannazzaro;A. Tesini;R. Tivey
Year: 1991 | Conference Paper |
Beryllium in JET: a report on the operational experience
K.J. Dietz;M.A. Pick;A.T. Peacock;K. Sonnenberg;J. Ehrenberg;G. Saibene;R. Sartori
The evaporation of beryllium inside the JET (Joint European Torus) has changed considerably the behavior of the machine and the plasma performance. Recovery from disruption was fast and density control was easily achieved. The operational space with respect to Z/sub eff/-values, dilution, density, and temperature could be considerably extended. The dilution was reduced and consequently the fusion ...Show More
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