NSTX-U Control System Upgrades

Erickson, K. G.; Gates, D. A.; Gerhardt, S. P.; Lawson, J. E.; Mozulay, R.; Sichta, P.; Tchilinguirian, G. J.

doi:10.1016/j.fusengdes.2014.04.069

Title: NSTX-U Control System Upgrades

Journal Article · Sun Jun 01 00:00:00 EDT 2014 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2014.04.069· OSTI ID:1172638

Erickson, K. G.; Gates, D. A.; Gerhardt, S. P.; Lawson, J. E.; Mozulay, R.; Sichta, P.; Tchilinguirian, G. J.

The National Spherical Tokamak Experiment (NSTX) is undergoing a wealth of upgrades (NSTX-U). These upgrades, especially including an elongated pulse length, require broad changes to the control system that has served NSTX well. A new fiber serial Front Panel Data Port input and output (I/O) stream will supersede the aging copper parallel version. Driver support for the new I/O and cyber security concerns require updating the operating system from Redhat Enterprise Linux (RHEL) v4 to RedHawk (based on RHEL) v6. While the basic control system continues to use the General Atomics Plasma Control System (GA PCS), the effort to forward port the entire software package to run under 64-bit Linux instead of 32-bit Linux included PCS modifications subsequently shared with GA and other PCS users. Software updates focused on three key areas: (1) code modernization through coding standards (C99/C11), (2) code portability and maintainability through use of the GA PCS code generator, and (3) support of 64-bit platforms. Central to the control system upgrade is the use of a complete real time (RT) Linux platform provided by Concurrent Computer Corporation, consisting of a computer (iHawk), an operating system and drivers (RedHawk), and RT tools (NightStar). Strong vendor support coupled with an extensive RT toolset influenced this decision. The new real-time Linux platform, I/O, and software engineering will foster enhanced capability and performance for NSTX-U plasma control.

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Research Organization:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 1172638

Report Number(s):: PPPL-5045; TRN: US1500484

Journal Information:: Fusion Engineering and Design, Vol. 89, Issue 6; Conference: IAEA 2013, Hefei (China), 6 May 2013; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 8 works

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Cited By (4)

Simultaneous feedback control of plasma rotation and stored energy on NSTX-U using neoclassical toroidal viscosity and neutral beam injection Goumiri, I. R.; Rowley, C. W.; Sabbagh, S. A. Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4976853	journal	May 2017
Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U Boyer, M. D.; Battaglia, D. J.; Mueller, D. Nuclear Fusion, Vol. 58, Issue 3 https://doi.org/10.1088/1741-4326/aaa4d0	journal	January 2018
Scenario development during commissioning operations on the National Spherical Torus Experiment Upgrade Battaglia, D. J.; Boyer, M. D.; Gerhardt, S. Nuclear Fusion, Vol. 58, Issue 4 https://doi.org/10.1088/1741-4326/aaa6e0	journal	February 2018
Feedback control design for non-inductively sustained scenarios in NSTX-U using TRANSP Boyer, M. D.; Andre, R. G.; Gates, D. A. Nuclear Fusion, Vol. 57, Issue 6 https://doi.org/10.1088/1741-4326/aa68e9	journal	April 2017

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