To control and optimize the power of the SPARC tokamak, we require information on the total radiated power of the plasma and its 2D and 3D spatial distribution. The SPARC bolometry diagnostic is being designed and built to measure the radiated power for controlling power balance, investigating the dissipation capabilities of various divertor concepts, and measuring the efficacy of the disruption thermal load mitigation. Proven resistive bolometer sensor technology will be used, with 248 lines of sight integrated into pinhole cameras in 20 different locations. This diversity of views will allow the bolometers to view the core, divertor, and particularly X-points of the plasma with high resolution. 14 of these camera locations are dedicated to 2D equilibrium radiated power, while the remaining six locations are designed to measure 3D radiated energy during disruptions. The bolometer sensor holders, pinhole camera boxes, and cabling have been designed to survive the high neutron flux (but low fluence) and up to 400 °C temperatures seen during operation and vacuum bake. The resistive bolometer sensors use Au absorbers with an Al heat conduction layer and C anti-reflective layer. These sensor chips are wire-bonded to an AlN circuit board, both of which are held inside a custom AlN and stainless steel bolometer holder. Design and optimization of the pinhole camera lines of sight are performed using Cherab. This work details the current state of the design of the SPARC bolometry diagnostic and its interfaces, as well as ongoing work to validate the design.
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http://dx.doi.org/10.1063/5.0219548 | DOI Listing |
Rev Sci Instrum
August 2024
Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.
To control and optimize the power of the SPARC tokamak, we require information on the total radiated power of the plasma and its 2D and 3D spatial distribution. The SPARC bolometry diagnostic is being designed and built to measure the radiated power for controlling power balance, investigating the dissipation capabilities of various divertor concepts, and measuring the efficacy of the disruption thermal load mitigation. Proven resistive bolometer sensor technology will be used, with 248 lines of sight integrated into pinhole cameras in 20 different locations.
View Article and Find Full Text PDFRev Sci Instrum
March 2023
York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, United KingdomOak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USAUnited Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon OX14 3DB, United KingdomCommonwealth Fusion Systems, Cambridge, Massachusetts 02139, USAMax Planck Institute for Plasma Physics, EURATOM Association, D-85748 Garching, Germany.
A prototype infrared video bolometer (IRVB) was successfully deployed in the Mega Ampere Spherical Tokamak Upgrade (MAST Upgrade or MAST-U), the first deployment of such a diagnostic in a spherical tokamak. The IRVB was designed to study the radiation around the lower x-point, another first in tokamaks, and has the potential to estimate emissivity profiles with spatial resolution beyond what is achievable with resistive bolometry. The system was fully characterized prior to installation on MAST-U, and the results are summarized here.
View Article and Find Full Text PDFRev Sci Instrum
March 2021
TAE Technologies, Inc., 19631 Pauling, Foothill Ranch, California 92610, USA.
In the current experimental device of TAE Technologies, C-2W (also called "Norman"), record breaking advanced beam-driven field-reversed configuration (FRC) plasmas are produced and sustained in steady state utilizing variable energy neutral beams (15-40 keV, total power up to 20 MW), advanced divertors, bias electrodes, and an active plasma control system. This fully operational experiment is coupled with a fully operational suite of advanced diagnostic systems. The suite consists of 60+ individual systems spanning 20 categories, including magnetic sensors, Thomson scattering, interferometry/polarimetry, spectroscopy, fast imaging, bolometry, reflectometry, charged and neutral particle analysis, fusion product detection, and electric probes.
View Article and Find Full Text PDFRev Sci Instrum
February 2021
Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USAÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), Lausanne CH-1015, SwitzerlandMIT Plasma Science and Fusion Center, Cambridge, Massachusetts 01239, USAInstituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Lisbon 1049-001, Portugal.
This paper presents techniques for evaluating the radiated power in JET disruptions. Disrupting plasmas are shown to have non-axisymmetric radiation profiles, motivating the re-evaluation of the standard techniques for calculating the total radiated power at JET using bolometry. Four single-channel bolometers at different toroidal locations are exploited to quantify the radiation asymmetry.
View Article and Find Full Text PDFRev Sci Instrum
November 2018
Max-Planck-Institut für Plasmaphysik, Boltzmannstrasse 2, D-85748 Garching, GermanyCCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB, United KingdomInstituto de Plasmas e Fuso Nuclear, Instituto Superior Tcnico, Universidade de Lisboa, Av. Rovisco Pais, 1049-001 Lisboa, PortugalOak Ridge National Laboratory, Oak Ridge, Tennessee 37830, USA.
The experimental method developed at ASDEX Upgrade for the determination of the intrinsic tungsten (W) density profile coupling data from the soft X-ray (SXR) diagnostic and vacuum-ultra-violet (VUV) spectroscopy has been upgraded for application to JET plasmas. The strong poloidal asymmetries in the SXR emission are modeled assuming a distribution, where is the flux coordinate, is the major radius, and is the fit parameter. The W density is calculated from the resulting 2D SXR emissivity maps accounting for contributions from a low-Z impurity (typically beryllium) and main ion with the assumption that their contributions are poloidally symmetric.
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