Keyword: plasma
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MOBL02 Real-Time Framework for ITER Control Systems controls, real-time, framework, operation 45
  • W.R. Lee, B. Bauvir, T.H. Tak, A. Žagar
    ITER Organization, St. Paul lez Durance, France
  • P. Karlovsek, M. Knap
    COSYLAB, Control System Laboratory, Ljubljana, Slovenia
  • S. Lee
    KFE, Daejeon, Republic of Korea
  • D.R. Makowski, P. Perek
    TUL-DMCS, Łódź, Poland
  • A. Winter
    MPI/IPP, Garching, Germany
  The ITER Real-Time Framework (RTF) is a middleware providing common services and capabilities to build real-time control applications in ITER such as the Plasma Control System (PCS) and plasma diagnostics. The RTF dynamically constructs applications at runtime from the configuration. The principal building blocks that compose an application process are called Function Blocks (FB), which follow a modular structure pattern. The application configuration defines the information that can influence control behavior, such as the connections among FBs, their corresponding parameters, and event handlers. The consecutive pipeline process in a busy-waiting mode and a data-driven pattern minimizes jitter and hardens the deterministic system behavior. In contrast, infrastructural capabilities are managed differently in the service layer using non-real-time threads. The deployment configuration covers the final placement of a program instance and thread allocation to the appropriate computing infrastructure. In this paper, we will introduce the architecture and design patterns of the framework as well as the real-life examples used to benchmark the RTF.  
slides icon Slides MOBL02 [3.192 MB]  
DOI • reference for this paper ※  
About • Received ※ 10 October 2021       Accepted ※ 11 November 2021       Issue date ※ 24 January 2022  
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WEAL01 Image Processing Alignment Algorithms for the Optical Thomson Scattering Laser at the National Ignition Facility alignment, laser, target, optics 528
  • A.A.S. Awwal, T.S. Budge, R.R. Leach, R.R. Lowe-Webb, V.J. Miller Kamm, S. Patankar, B.P. Patel, K.C. Wilhelmsen
    LLNL, Livermore, California, USA
  Funding: *This work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.
Understanding plasma performance in the world’s largest and most energetic laser facility, the National Ignition Facility (NIF), is an important step to achieving the goal of inertial confinement fusion in a laboratory setting. The optical Thompson scattering (OTS) laser has been developed to understand the target implosion physics, especially for under-dense plasma conditions. A 5w probe beams can be set up for diagnosing various plasma densities. Just as the NIF laser with 192 laser beams are precisely aligned, the OTS system also requires precision alignment using a series of automated closed loop control steps. CCD images from the OTS laser (OTSL) beams are analyzed using a suite of image processing algorithm. The algorithms provide beam position measurements that are used to control motorized mirrors that steer beams to their defined desired location. In this paper, several alignment algorithms will be discussed with details on how they take advantage of various types of fiducials such as diffraction rings, contrasting squares and circles, octagons and very faint 5w laser beams.
*This is released as LLNL-ABS-821809
slides icon Slides WEAL01 [1.303 MB]  
DOI • reference for this paper ※  
About • Received ※ 08 October 2021       Revised ※ 18 October 2021       Accepted ※ 21 November 2021       Issue date ※ 14 March 2022
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