US Instrumentation & Controls - Home | US ITERC.pdfoccur at the JET tokamak. Photo: US ITER Neutron...

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The US instrumentation and controls scope spans 7 different hardware systems. Image: iStock US Contribution The US is responsible for providing instrumentation and controls (I&C) for the following seven US systems: Tokamak cooling water system, electron cyclotron transmission lines, ion cyclotron transmission lines, diagnostics, pellet injection, and vacuum auxiliary systems. The US does not provide I&C for magnet systems, the steady state electrical network, or for disruption mitigation. Overview The work scope for instrumentation and controls (I&C) includes: conceptual, preliminary, and final I&C design; I&C software design; I&C hardware and software procurement; I&C equipment fabrication; and I&C qualification and testing. Distributed real-time control of ITER plant systems is based on the EPICS (Experimental Physics and Industrial Control System) for non-safety systems. Hierarchical control and exception handling is provided to the ITER Plasma Control System (PCS) for control of plasma shape and kinetic parameters for electron cyclotron and ion cyclotron plasma heating systems, pellet injection and disruption mitigation systems. Nuclear safety functions are based on the HIMA Planar4 logic solver contained within a cubicle assembly and qualified based on IEC 61513 I&C safety lifecycle for nuclear power plants. All I&C equipment including electronics and instruments must be designed in compliance with the French Nuclear Safety Authority (ASN) including International Electrotechnical Commission (IEC) and Institute of Electrical and Electronics Engineers (IEEE) requirements related to Nuclear Power Plants as a nuclear licensed fusion reactor. 1 st Plasma Scope The I&C scope for 1st plasma includes development for all I&C systems through final design. The I&C fabrication scope for 1st plasma includes all I&C for the tokamak cooling water system vacuum vessel primary heating transfer system, draining and drying systems; a portion of I&C for the roughing pumps and service vacuum system, plus all I&C for the cryo-guard vacuum system; all I&C for the ion cyclotron transmission lines in the RF building; and, a portion of I&C for the 8 electron cyclotron transmission lines. Status Final Design Review was completed for ion cyclotron transmission lines first plasma hardware. Other first plasma designs are underway. The US is responsible for providing instrumentation and controls (I&C) for seven US systems. Image: US ITER SVS pressure sensor electronics testing. Image: US ITER Instrumentation & Controls US ITER Project Office • 1055 Commerce Park • Oak Ridge, Tennessee 37830-6483 US www.usiter.org

Transcript of US Instrumentation & Controls - Home | US ITERC.pdfoccur at the JET tokamak. Photo: US ITER Neutron...

Page 1: US Instrumentation & Controls - Home | US ITERC.pdfoccur at the JET tokamak. Photo: US ITER Neutron flux preliminary results for a wall-mounted cubicle in the level 1 gallery. Image:

The US instrumentation and controls scope spans 7 different hardware systems. Image: iStock

US Contribution The US is responsible for providing instrumentation and controls (I&C) for the following seven US systems: Tokamak cooling water system, electron cyclotron transmission lines, ion cyclotron transmission lines, diagnostics, pellet injection, and vacuum auxiliary systems. The US does not provide I&C for magnet systems, the steady state electrical network, or for disruption mitigation.

OverviewThe work scope for instrumentation and controls (I&C) includes: conceptual, preliminary, and final I&C design; I&C software design; I&C hardware and software procurement; I&C equipment fabrication; and I&C qualification and testing. Distributed real-time control of ITER plant systems is based on the EPICS (Experimental Physics and Industrial Control System) for non-safety systems. Hierarchical control and exception handling is provided to the ITER Plasma Control System (PCS) for control of plasma shape and kinetic parameters for electron cyclotron and ion cyclotron plasma heating systems, pellet injection and disruption mitigation systems. Nuclear safety functions are based on the HIMA Planar4 logic solver contained within a cubicle assembly and qualified based on IEC 61513 I&C safety lifecycle for nuclear power plants. All I&C equipment including electronics and instruments must be designed in compliance with the French Nuclear Safety Authority (ASN) including International Electrotechnical Commission (IEC) and Institute of Electrical and Electronics Engineers (IEEE) requirements related to Nuclear Power Plants as a nuclear licensed fusion reactor.

1st Plasma ScopeThe I&C scope for 1st plasma includes development for all I&C systems through final design. The I&C fabrication scope for 1st plasma includes all I&C for the tokamak cooling water system vacuum vessel primary heating transfer system, draining and drying systems; a portion of I&C for the roughing pumps and service vacuum system, plus all I&C for the cryo-guard vacuum system; all I&C for the ion cyclotron transmission lines in the RF building; and, a portion of I&C for the 8 electron cyclotron transmission lines.

StatusFinal Design Review was completed for ion cyclotron transmission lines first plasma hardware. Other first plasma designs are underway.

The US is responsible for providing instrumentation and controls (I&C) for seven US systems . Image: US ITER

SVS pressure sensor electronics testing. Image: US ITER

Instrumentation & Controls

US ITER Project Office • 1055 Commerce Park • Oak Ridge, Tennessee 37830-6483

US

www.usiter.org

Page 2: US Instrumentation & Controls - Home | US ITERC.pdfoccur at the JET tokamak. Photo: US ITER Neutron flux preliminary results for a wall-mounted cubicle in the level 1 gallery. Image:

USInstrumentation & Controls

Kurt VetterUS ITER Project Office Instrumentation & Controls Team Leader

Oak Ridge National Laboratory [email protected] | 865-241-9702

Prototype residual gas analyzer testing at ORNL validated quadrupole mass

spectrometer performance; further testing will occur at the JET tokamak. Photo: US ITER

Neutron flux preliminary results for a wall-mounted cubicle in the level 1 gallery.

Image: US ITER

Technical Description• Tokamak Cooling Water I&C

I&C will be provided to six (6) TCWS sub-systems, Vacuum Vessel Primary Heat Transfer System (VV PHTS), Draining (DR), Drying (DY), Integrated Blanket, ELM, Diverter Primary Heat Transfer System (IBED PHTS), Neutral Beam Injection Primary Heat Transfer System (NBI PHTS) and the Chemical & Volume Control System (CVCS).

• Vacuum I&CI&C will include the overall vacuum instrumentation and control system (VICS), and development of custom radiation-hardened electronics, as well as VICS-supervised I&C systems for the Cryo-Guard Vacuum System, Service Vacuum System, Electron Cyclotron Heating, Ion Cyclotron Heating, and Type 2 Diagnostics. These I&C systems span from conventional programmable logic controllers to custom electronics for high radiation/high magnetic field areas. The I&C systems monitor vacuum gauges and other instruments and actuate vacuum and gas-supply valves. For the roughing pumps system, over 50 pumps of five different pumping technologies will be controlled and monitored.

• Ion Cyclotron Heating I&CI&C will provide an interface to fast arc detection, real-time processing of a multi-variable state-space impedance control system to enable maximum radio frequency power transmission to the plasma, calorimetric measurements and control of 124 water cooling loops and 14 gas cooling loops.

• Electron Cyclotron Heating I&CI&C will provide fast arc detection, calorimetric power measurements, polarization control, data acquisition, monitoring and control of 584 cooling loops for the 24 ECH transmission lines supplied by the US.

• Pellet Injection I&CI&C scope consists of control of actuators, and monitoring of gas and pressure sensors under real-time interaction with the ITER plasma control system.

• Diagnostics I&CI&C scope consists of development of diagnostic residual gas analyzer (DRGA) readout system, development of custom impedance matching of quadrapole mass spectrometer RF controller to enable operation in high radiation environment, plus coordination of US diagnostic infrastructure system architecture, common I&C solutions, expert guidance on ITER standards and procedures.

www.usiter.org • www.iter.org • www.doe.gov • www.science.doe.gov