Advanced data acquisition system implementation for the ITER Neutron Diagnostic use case using EPICS and FlexRIO technology on a PXIe platform

Sanz Hernando, Diego and Ruiz González, Mariano and Castro, R. and Vega, J. and Afif, M. and Monroe, M. and Simrock, S. and Debelle, T. and Marawar, R. and Glass, B. (2014). Advanced data acquisition system implementation for the ITER Neutron Diagnostic use case using EPICS and FlexRIO technology on a PXIe platform. In: "19th Real Time Conference, May 26-30, 2014", 26/05/2014 - 30/05/2014, Nara, Japan. ISBN 978-1-4799-3659-5. pp. 1-2. https://doi.org/10.1109/RTC.2014.7097486.

Description

Title: Advanced data acquisition system implementation for the ITER Neutron Diagnostic use case using EPICS and FlexRIO technology on a PXIe platform
Author/s:
  • Sanz Hernando, Diego
  • Ruiz González, Mariano
  • Castro, R.
  • Vega, J.
  • Afif, M.
  • Monroe, M.
  • Simrock, S.
  • Debelle, T.
  • Marawar, R.
  • Glass, B.
Item Type: Presentation at Congress or Conference (Article)
Event Title: 19th Real Time Conference, May 26-30, 2014
Event Dates: 26/05/2014 - 30/05/2014
Event Location: Nara, Japan
Title of Book: 19th IEEE-NPSS Real Time Conference (RT), 2014
Date: 2014
ISBN: 978-1-4799-3659-5
Subjects:
Freetext Keywords: Tokamak devices, data acquisition, neutron flux, nuclear engineering computing, plasma toroidal confinement
Faculty: E.T.S.I. y Sistemas de Telecomunicación (UPM)
Department: Ingeniería Telemática y Electrónica
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

In the framework of the ITER Control Breakdown Structure (CBS), Plant System Instrumentation & Control (I&C) defines the hardware and software required to control one or more plant systems [1]. For diagnostics, most of the complex Plant System I&C are to be delivered by ITER Domestic Agencies (DAs). As an example for the DAs, ITER Organization (IO) has developed several use cases for diagnostics Plant System I&C that fully comply with guidelines presented in the Plant Control Design Handbook (PCDH) [2]. One such use case is for neutron diagnostics, specifically the Fission Chamber (FC), which is responsible for delivering time-resolved measurements of neutron source strength and fusion power to aid in assessing the functional performance of ITER [3]. ITER will deploy four Fission Chamber units, each consisting of three individual FC detectors. Two of these detectors contain Uranium 235 for Neutron detection, while a third "dummy" detector will provide gamma and noise detection. The neutron flux from each MFC is measured by the three methods: . Counting Mode: measures the number of individual pulses and their location in the record. Pulse parameters (threshold and width) are user configurable. . Campbelling Mode (Mean Square Voltage): measures the RMS deviation in signal amplitude from its average value. .Current Mode: integrates the signal amplitude over the measurement period

Funding Projects

TypeCodeAcronymLeaderTitle
Government of SpainENE2012-38970-C04-04UnspecifiedMinisterio de Economía y CompetitividadUnspecified

More information

Item ID: 35385
DC Identifier: http://oa.upm.es/35385/
OAI Identifier: oai:oa.upm.es:35385
DOI: 10.1109/RTC.2014.7097486
Official URL: http://rt2014.rcnp.osaka-u.ac.jp/
Deposited by: Memoria Investigacion
Deposited on: 31 Mar 2016 17:10
Last Modified: 31 Mar 2016 17:10
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