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Title: Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System

Abstract

The current design for the ITER Low Field Side Reflectometer (LFSR) diagnostic system contains six circular waveguides that function as both launch and receive antennas. The front end of LFSR system, interfacing with the plasma facing DFW and its supporting diagnostic shielding Modules (DSM), is integrated into Equatorial Port Plug 11(EPP#11). In-vessel LFSR configuration is mainly divided into two sections, i.e. Front Antenna Unit (FAU) and in-vessel Transmission Line (TL) components. During plasma normal operation, the 14 MeV neutrons from D-T fusion reactions penetrate into the port plug and LFSR components. Neutronics code ATTILA is used for assessing the volumetric heating of in-vessel components. The maximum normal heat load due to radiation and the charge exchange from plasma is 0.35 MW/m 2, which has to be applied on those surfaces affected by a viewing factor consistent with the aperture surface position and orientation. The front antenna unit (FAU) needs the active cooling to handle the radiant and nuclear heating from the plasma. Due to the specific viewing aperture layout at the front-end of in-vessel LFSR, the cooling channel design is challenging. The thermal-hydraulic iterations are performed to achieve the desirable temperature distribution of the water cooled front antenna units. Themore » progressive ratcheting effects of the FAU subjected to cyclic thermal loading are examined by the preliminary non-linear elastic-plastic analysis.« less

Authors:
ORCiD logo [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1502966
Grant/Contract Number:  
AC02-09CH11466
Resource 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
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; front antenna unit; heat loads; cooling design; progressive deformation or ratcheting

Citation Formats

Wang, Wenping, Zolfaghari, Ali, Neilson, Hutch, Klabacha, Jonathan, Khodak, Andrei, Basile, Allan, Smith, Mark, and Zhai, Yuhu. Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System. United States: N. p., 2019. Web. doi:10.1016/j.fusengdes.2019.02.062.
Wang, Wenping, Zolfaghari, Ali, Neilson, Hutch, Klabacha, Jonathan, Khodak, Andrei, Basile, Allan, Smith, Mark, & Zhai, Yuhu. Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System. United States. doi:10.1016/j.fusengdes.2019.02.062.
Wang, Wenping, Zolfaghari, Ali, Neilson, Hutch, Klabacha, Jonathan, Khodak, Andrei, Basile, Allan, Smith, Mark, and Zhai, Yuhu. Wed . "Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System". United States. doi:10.1016/j.fusengdes.2019.02.062.
@article{osti_1502966,
title = {Thermal Loads and Cooling Design for ITER in-Port Low Field Side Reflectometer Diagnostic System},
author = {Wang, Wenping and Zolfaghari, Ali and Neilson, Hutch and Klabacha, Jonathan and Khodak, Andrei and Basile, Allan and Smith, Mark and Zhai, Yuhu},
abstractNote = {The current design for the ITER Low Field Side Reflectometer (LFSR) diagnostic system contains six circular waveguides that function as both launch and receive antennas. The front end of LFSR system, interfacing with the plasma facing DFW and its supporting diagnostic shielding Modules (DSM), is integrated into Equatorial Port Plug 11(EPP#11). In-vessel LFSR configuration is mainly divided into two sections, i.e. Front Antenna Unit (FAU) and in-vessel Transmission Line (TL) components. During plasma normal operation, the 14 MeV neutrons from D-T fusion reactions penetrate into the port plug and LFSR components. Neutronics code ATTILA is used for assessing the volumetric heating of in-vessel components. The maximum normal heat load due to radiation and the charge exchange from plasma is 0.35 MW/m2, which has to be applied on those surfaces affected by a viewing factor consistent with the aperture surface position and orientation. The front antenna unit (FAU) needs the active cooling to handle the radiant and nuclear heating from the plasma. Due to the specific viewing aperture layout at the front-end of in-vessel LFSR, the cooling channel design is challenging. The thermal-hydraulic iterations are performed to achieve the desirable temperature distribution of the water cooled front antenna units. The progressive ratcheting effects of the FAU subjected to cyclic thermal loading are examined by the preliminary non-linear elastic-plastic analysis.},
doi = {10.1016/j.fusengdes.2019.02.062},
journal = {Fusion Engineering and Design},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {3}
}

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This content will become publicly available on March 6, 2020
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