Prototyping phase of the high heat flux scraper element of Wendelstein 7-X

Boscary, Jean; Greuner, Henri; Ehrke, G.; Boswirth, Bernd; Wang, Zhongwei; Clark, Emily; Lumsdaine, A.; Tretter, Jorg; McGinnis, D.; Lore, Jeremy D.; Ekici, K.

doi:10.1016/j.fusengdes.2016.02.001

Title: Prototyping phase of the high heat flux scraper element of Wendelstein 7-X

Journal Article · Thu Mar 24 00:00:00 EDT 2016 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2016.02.001· OSTI ID:1394578

Boscary, Jean ^[1]; Greuner, Henri ^[1]; Ehrke, G. ^[2]; Boswirth, Bernd ^[1]; Wang, Zhongwei ^[1]; Clark, Emily ^[3]; Lumsdaine, A. ^[4]; Tretter, Jorg ^[1];

^[4];

^[4]; Ekici, K. ^[3]

Max Planck Institute for Plasma Physics, Garching (Germany)
Max Planck Institute for Plasma Physics, Greifswald (Germany)
Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The water-cooled high heat flux scraper element aims to reduce excessive heat loads on the target element ends of the actively cooled divertor of Wendelstein 7-X. Its purpose is to intercept some of the plasma fluxes both upstream and downstream before they reach the divertor surface. The scraper element has 24 identical plasma facing components (PFCs) divided into 6 modules. One module has 4 PFCs hydraulically connected in series by 2 water boxes. A PFC, 247 mm long and 28 mm wide, has 13 monoblocks made of CFC NB31 bonded by hot isostatic pressing onto a CuCrZr cooling tube equipped with a copper twisted tape. 4 full-scale prototypes of PFCs have been successfully tested in the GLADIS facility up to 20 MW/m². The difference observed between measured and calculated surface temperatures is probably due to the inhomogeneity of CFC properties. The design of the water box prototypes has been detailed to allow the junction between the cooling pipe of the PFCs and the water boxes by internal orbital welding. In conclusion, the prototypes are presently under fabrication.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC); Federal Ministry of Education and Research of the Federal Republic of Germany

Grant/Contract Number:: AC05-00OR22725; 03FUS0014A

OSTI ID:: 1394578

Journal Information:: Fusion Engineering and Design, Vol. 109-111, Issue PA; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 7 works

Citation information provided by
Web of Science

References (13)

Wendelstein 7-X—Status of the project and commissioning planning Gasparotto, Maurizio; Baylard, Christophe; Bosch, Hans-Stephan Fusion Engineering and Design, Vol. 89, Issue 9-10 https://doi.org/10.1016/j.fusengdes.2014.02.075	journal	October 2014
Progress in the design and development of a test divertor (TDU) for the start of W7-X operation Peacock, A.; Greuner, H.; Hurd, F. Fusion Engineering and Design, Vol. 84, Issue 7-11 https://doi.org/10.1016/j.fusengdes.2009.01.053	journal	June 2009
Design improvement of the target elements of Wendelstein 7-X divertor Boscary, J.; Peacock, A.; Friedrich, T. Fusion Engineering and Design, Vol. 87, Issue 7-8 https://doi.org/10.1016/j.fusengdes.2012.03.034	journal	August 2012
Design and Analysis of Divertor Scraper Elements for the W7-X Stellarator Lore, Jeremy D.; Andreeva, Tamara; Boscary, Jean IEEE Transactions on Plasma Science, Vol. 42, Issue 3 https://doi.org/10.1109/TPS.2014.2303649	journal	March 2014
Design of the Wendelstein 7-X inertially cooled Test Divertor Unit Scraper Element Lumsdaine, Arnold; Boscary, Jean; Fellinger, Joris Fusion Engineering and Design, Vol. 98-99 https://doi.org/10.1016/j.fusengdes.2015.02.012	journal	October 2015
Assessment of CFC grades under thermal fatigue for the ITER inner vertical target Richou, M.; Missirlian, M.; Riccardi, B. Physica Scripta, Vol. T145 https://doi.org/10.1088/0031-8949/2011/T145/014082	journal	December 2011
Pulsed thermography inspection of the target elements for the W7-X divertor Traxler, H.; Schuler, P. Physica Scripta, Vol. T128 https://doi.org/10.1088/0031-8949/2007/T128/047	journal	March 2007
Fabrication and testing of W7-X pre-series target elements Boscary, J.; Böswirth, B.; Greuner, H. Physica Scripta, Vol. T128 https://doi.org/10.1088/0031-8949/2007/T128/037	journal	March 2007
Design, performance and construction of a 2MW ion beam test facility for plasma facing components Greuner, H.; Bolt, H.; Böswirth, B. Fusion Engineering and Design, Vol. 75-79 https://doi.org/10.1016/j.fusengdes.2005.06.021	journal	November 2005
Thermal-fluid modeling of single- and two-phase flows in the W7-X high heat flux divertor scraper element Clark, E.; Ekici, K.; Lumsdaine, A. 2015 IEEE 26th Symposium on Fusion Engineering (SOFE) https://doi.org/10.1109/SOFE.2015.7482430	conference	May 2015
Overview of Design and Analysis Activities for the W7-X Scraper Element Lumsdaine, A.; Bjorholm, T.; Harris, J. IEEE Transactions on Plasma Science, Vol. 44, Issue 9 https://doi.org/10.1109/TPS.2016.2598486	journal	September 2016
Design analysis and manufacturing of the cooling lines of the in vessel components of WENDELSTEIN 7-X Mendelevitch, B.; Vorköper, A.; Boscary, J. Fusion Engineering and Design, Vol. 86, Issue 9-11 https://doi.org/10.1016/j.fusengdes.2011.02.064	journal	October 2011
Development activities of the high heat flux scraper element Boscary, J.; Lore, J.; Lumsdaine, A. Fusion Engineering and Design, Vol. 98-99 https://doi.org/10.1016/j.fusengdes.2014.12.019	journal	October 2015

Cited By (1)

Development and Performance of Tungsten-Coated Graphitic Foam for Plasma-Facing Components Youchison, D. L.; Coenen, J. W.; Gray, T. K. Fusion Science and Technology, Vol. 75, Issue 6 https://doi.org/10.1080/15361055.2019.1607706	journal	May 2019

Similar Records

Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper

Conference · Sun Apr 01 00:00:00 EDT 2018 · OSTI ID:1394578

Boscary, J.; Greuner, Henri; Ehrke, Gunnar; +10 more

Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element

Journal Article · Fri Jul 28 00:00:00 EDT 2017 · Fusion Engineering and Design · OSTI ID:1394578

Clark, Emily; Lumsdaine, Arnold; Boscary, Jean; +2 more

High heat-flux response of high-conductivity graphitic foam monoblocks

Conference · Tue Jan 01 00:00:00 EST 2019 · Fusion Engineering and Design · OSTI ID:1394578

Youchison, Dennis; Gehrig, Monica; Lumsdaine, Arnold; +3 more

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Stellarator
Wendelstein 7-X
Plasma facing component
Divertor
Monoblock

Title: Prototyping phase of the high heat flux scraper element of Wendelstein 7-X

Citation Formats

References (13)

Cited By (1)

Similar Records

Related Subjects