skip to main content

DOE PAGESDOE PAGES

This content will become publicly available on February 7, 2019

Title: Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2

In this work, Wendelstein 7-X (W7-X) is the world’s largest superconducting nuclear fusion experiment of the optimized stellarator type. In the first Operation Phase (OP1.1) helium and hydrogen plasmas were studied in limiter configuration. The heating energy was limited to 4 MJ and the main purpose of that campaign was the integral commissioning of the machine and diagnostics, which was achieved very successfully. Already from the beginning a comprehensive set of diagnostics was available to study the plasma. On the path towards high-power, high-performance plasmas, W7-X will be stepwise upgraded from an inertially cooled (OP1.2, limited to 80 MJ) to an actively cooled island divertor (OP2, 10 MW steady-state plasma operation). The machine is prepared for OP1.2 with 10 inertially cooled divertor units, and the experimental campaign has started recently.The paper describes a subset of diagnostics which will be available for OP1.2 to study the plasma edge, divertor and scrape-off layer physics including those already available for OP1.1, plus modifications, upgrades and new systems. In conclusion, the focus of this summary will be on technical and engineering aspects, like feasibility and assembly but also on reliability, thermal loads and shielding against magnetic fields.
Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; more »; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; « less
Publication Date:
Grant/Contract Number:
AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Name: Fusion Engineering and Design; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE
Contributing Orgs:
the W7-X Team
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Wendelstein 7-X; Diagnostics; Plasma edge; SOL; Steady-state operation
OSTI Identifier:
1435175

Hathiramani, D., Ali, A., Anda, G., Barbui, T., Biedermann, C., Charl, A., Chauvin, D., Czymek, G., Dhard, C. P., Drewelow, P., Dudek, A., Effenberg, F., Ehrke, G., Endler, M., Ennis, D. A., Fellinger, J., Ford, O., Freundt, S., Gradic, D., Grosser, K., Harris, J., Hölbe, H., Jakubowski, M. W., Knaup, M., Kocsis, G., König, R., Krause, M., Kremeyer, T., Kornejew, P., Krychowiak, M., Lambertz, H. T., Jenzsch, H., Mayer, M., Mohr, S., Neubauer, O., Otte, M., Perseo, V., Pilopp, D., Rudischhauser, L., Schmitz, O., Schweer, B., Schülke, M., Stephey, L., Szepesi, T., Terra, A., Toth, M., Wenzel, U., Wurden, G. A., Zoletnik, S., and Pedersen, T. Sunn. Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2. United States: N. p., Web. doi:10.1016/j.fusengdes.2018.02.013.
Hathiramani, D., Ali, A., Anda, G., Barbui, T., Biedermann, C., Charl, A., Chauvin, D., Czymek, G., Dhard, C. P., Drewelow, P., Dudek, A., Effenberg, F., Ehrke, G., Endler, M., Ennis, D. A., Fellinger, J., Ford, O., Freundt, S., Gradic, D., Grosser, K., Harris, J., Hölbe, H., Jakubowski, M. W., Knaup, M., Kocsis, G., König, R., Krause, M., Kremeyer, T., Kornejew, P., Krychowiak, M., Lambertz, H. T., Jenzsch, H., Mayer, M., Mohr, S., Neubauer, O., Otte, M., Perseo, V., Pilopp, D., Rudischhauser, L., Schmitz, O., Schweer, B., Schülke, M., Stephey, L., Szepesi, T., Terra, A., Toth, M., Wenzel, U., Wurden, G. A., Zoletnik, S., & Pedersen, T. Sunn. Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2. United States. doi:10.1016/j.fusengdes.2018.02.013.
Hathiramani, D., Ali, A., Anda, G., Barbui, T., Biedermann, C., Charl, A., Chauvin, D., Czymek, G., Dhard, C. P., Drewelow, P., Dudek, A., Effenberg, F., Ehrke, G., Endler, M., Ennis, D. A., Fellinger, J., Ford, O., Freundt, S., Gradic, D., Grosser, K., Harris, J., Hölbe, H., Jakubowski, M. W., Knaup, M., Kocsis, G., König, R., Krause, M., Kremeyer, T., Kornejew, P., Krychowiak, M., Lambertz, H. T., Jenzsch, H., Mayer, M., Mohr, S., Neubauer, O., Otte, M., Perseo, V., Pilopp, D., Rudischhauser, L., Schmitz, O., Schweer, B., Schülke, M., Stephey, L., Szepesi, T., Terra, A., Toth, M., Wenzel, U., Wurden, G. A., Zoletnik, S., and Pedersen, T. Sunn. 2018. "Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2". United States. doi:10.1016/j.fusengdes.2018.02.013.
@article{osti_1435175,
title = {Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2},
author = {Hathiramani, D. and Ali, A. and Anda, G. and Barbui, T. and Biedermann, C. and Charl, A. and Chauvin, D. and Czymek, G. and Dhard, C. P. and Drewelow, P. and Dudek, A. and Effenberg, F. and Ehrke, G. and Endler, M. and Ennis, D. A. and Fellinger, J. and Ford, O. and Freundt, S. and Gradic, D. and Grosser, K. and Harris, J. and Hölbe, H. and Jakubowski, M. W. and Knaup, M. and Kocsis, G. and König, R. and Krause, M. and Kremeyer, T. and Kornejew, P. and Krychowiak, M. and Lambertz, H. T. and Jenzsch, H. and Mayer, M. and Mohr, S. and Neubauer, O. and Otte, M. and Perseo, V. and Pilopp, D. and Rudischhauser, L. and Schmitz, O. and Schweer, B. and Schülke, M. and Stephey, L. and Szepesi, T. and Terra, A. and Toth, M. and Wenzel, U. and Wurden, G. A. and Zoletnik, S. and Pedersen, T. Sunn},
abstractNote = {In this work, Wendelstein 7-X (W7-X) is the world’s largest superconducting nuclear fusion experiment of the optimized stellarator type. In the first Operation Phase (OP1.1) helium and hydrogen plasmas were studied in limiter configuration. The heating energy was limited to 4 MJ and the main purpose of that campaign was the integral commissioning of the machine and diagnostics, which was achieved very successfully. Already from the beginning a comprehensive set of diagnostics was available to study the plasma. On the path towards high-power, high-performance plasmas, W7-X will be stepwise upgraded from an inertially cooled (OP1.2, limited to 80 MJ) to an actively cooled island divertor (OP2, 10 MW steady-state plasma operation). The machine is prepared for OP1.2 with 10 inertially cooled divertor units, and the experimental campaign has started recently.The paper describes a subset of diagnostics which will be available for OP1.2 to study the plasma edge, divertor and scrape-off layer physics including those already available for OP1.1, plus modifications, upgrades and new systems. In conclusion, the focus of this summary will be on technical and engineering aspects, like feasibility and assembly but also on reliability, thermal loads and shielding against magnetic fields.},
doi = {10.1016/j.fusengdes.2018.02.013},
journal = {Fusion Engineering and Design},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {2}
}