Real-time plasma position reflectometry system development and integration on COMPASS tokamak
Introduction
Microwave based diagnostics present a viable solution in plasma position determination, being able to provide robust measurements even in the presence of turbulence. Microwave reflectometry was proposed for ITER [1] as a diagnostic to measure the plasma boundary position (gap control) and is presently envisaged for DEMO [2]. In particular, Plasma position reflectometry (PPR) is convenient for separatrix position based control applications [3] as it works on ordinary mode (O-mode), thus not depending on knowledge of the magnetic field. The technique demonstration was conducted on ASDEX Upgrade, first by probing the plasma at the low-field side (LFS) [4] and latter at LFS and high-field side (HFS) simultaneously [5], [6]. Considering the available O-mode reflectometry diagnostic, the demanding RTCS implemented in MARTe and the relevant plasma regimes achievable in COMPASS tokamak, this device provides the right environment to validate further PPR as a plasma position control technique, in line with the work being conducted on other fusion devices [7].
The COMPASS tokamak, installed in IPP-CAS Prague, is a compact divertor device with an ITER-relevant geometry capable of H-mode operation and targeting pedestal and edge physics studies for ITER [8]. The real-time control system (RTCS) implementation was done on MARTe [9], controlling vertical and horizontal plasma position, equilibrium, shaping and plasma current using magnetic diagnostics and plasma density based on microwave interferometer [10], [11]. Besides other diagnostics, the device is equipped with a multi-band O-mode reflectometer [12]. The Multi-threaded Application Real-Time executor, known as MARTe, is a real-time (RT) framework based on the BaseLib2 C++ library and is employed into the deployment of control systems for critical applications [13]. This framework, employed on different Controlled Nuclear Fusion devices [11] as a robust solution, is compliant with Portable Operating System Interface (POSIX) standards for real-time application interfaces and was ported to several operating systems [13], including Linux, Linux/RTAI, VxWorks, Solaris, OS X and MS Windows.
Section snippets
Deployment setup and requirements
The PPR system implementation on COMPASS tokamak required the seamless integration of the microwave reflectometry diagnostic on the RTCS, to provide the controller with robust position estimates within the allowed latency. This section describes the COMPASS experimental infrastructure systems relevant for the present application, in particular the real-time control system and the microwave reflectometry diagnostic, depicted in Fig. 1.
Diagnostic integration
The integration of the reflectometry diagnostic on the RTCS was achieved through modifications of the already existing infrastructure in conjunction with the introduction of new devices and features at hardware and software levels. To expedite the implementation time and to minimise the impact on COMPASS operation, priority was given to the usage of devices already used and tested in the facility, along with commercial off-the-shelf (COTS) solutions. This section describes the integration of
Diagnostic operation
The PPR system herein described was integrated into the RTCS and operated during a set of COMPASS discharges to infer its capability to reliably meet the control implementation requirements and possible impact on the RTCS performance. To assess the performance of the system and the response of the thread synchronisation mechanisms in play, the latencies and execution times were stored in both MARTe nodes. Discharge #19679 is used to illustrate the behaviour of the system in real operation
Conclusions
The system herein described was able to successfully integrate the already existing O-mode microwave reflectometer in the COMPASS real-time diagnostic network, making it usable for position feedback experiments, providing MARTe-Main controller with a PPR based radial position estimation. MARTe framework largely expedited the design, development and commissioning of the real-time application, due to its well-defined software block structure. Its modular approach facilitated the testing and
Declaration of interests
None.
Declaration of Competing Interest
The authors report no declarations of interest.
Acknowledgments
IPFN-IST activities received financial support from Fundação para a Ciência e a Tecnologia – FCT through projects UIDB/50010/2020 and UIDP/50010/2020. IPP-CAS activities have been funded by Ministerstvo Školství, Mládeže a Tělovýchovy – MSMT, grant #LM2015045 and within the framework of the project COMPASS-U: Tokamak for cutting-edge fusion research (No. CZ.02.1.01/0.0/0.0/16_019/0000768), co-funded from European structural and investment funds (Czech Republic). The views and opinions expressed
References (24)
- et al.
Diagnostics for plasma control – from iter to demo
Fusion Eng. Des.
(2019) - et al.
Overview of the COMPASS diagnostics
Fusion Eng. Des.
(2011) - et al.
Upgrade of the COMPASS tokamak real-time control system
Fusion Eng. Des.
(2014) - et al.
Overview of the COMPASS CODAC system
Fusion Eng. Des.
(2014) - et al.
Upgrade of the compass tokamak microwave reflectometry system with I/Q modulation and detection
Fusion Eng. Des.
(2017) - et al.
Analysis of separatrix plasma parameters using local and multi-machine databases
J. Nucl. Mater.
(1999) - et al.
Plasma density control in real-time on the COMPASS tokamak
Fusion Eng. Des.
(2015) - et al.
Diagnostics for Experimental Thermonuclear Reactors 2 – ITER Position Control Reflectometry – Conceptual Design
(1998) - et al.
Plasma position measurements from ordinary FM-CW reflectometry on ASDEX Upgrade
Rev. Sci. Instr.
(2003) - et al.
Reflectometry-based plasma position feedback control demonstration at ASDEX Upgrade
Nucl. Fusion
(2012)
Enhancement of the ASDEX upgrade real-time plasma position reflectometry diagnostic
IEEE Trans. Nucl. Sci.
Real-time reflectometry—an ASDEX Upgrade DCS plugin App for plasma position and shape feedback control
Fusion Eng. Des.
Cited by (3)
An optical-input Maximum Likelihood Estimation feedback system demonstrated on tokamak horizontal equilibrium control
2023, Fusion Engineering and DesignPlasma position measurements by O-mode and X-mode reflectometry systems in tokamak plasmas
2023, Review of Scientific Instruments