Performance analysis of Rogowski coils and the measurement of the total toroidal current in the ITER machine
- 1. Dipartimento di Ingegneria Elettrica e Tecnologie dell'Informazione, Università Federico II, Napoli (Italy)
- 2. Scuola di Ingegneria, Università della Basilicata, Potenza (Italy)
- 3. Dipartimento di Economia, Ingegneria, Società e Impresa, Università della Tuscia, Viterbo (Italy)
- 4. Fusion for Energy (F4E), Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)
- 5. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)
Description
The paper carries out a comprehensive study of the performances of Rogowski coils. It describes methodologies that were developed in order to assess the capabilities of the Continuous External Rogowski (CER), which measures the total toroidal current in the ITER machine. Even though the paper mainly considers the CER, the contents are general and relevant to any Rogowski sensor.
The CER consists of two concentric helical coils which are wound along a complex closed path. Modelling and computational activities were performed to quantify the measurement errors, taking detailed account of the ITER environment. The geometrical complexity of the sensor is accurately accounted for and the standard model which provides the classical expression to compute the flux linkage of Rogowski sensors is quantitatively validated. Then, in order to take into account the non-ideality of the winding, a generalized expression, formally analogue to the classical one, is presented. Models to determine the worst case and the statistical measurement accuracies are hence provided. The following sources of error are considered: effect of the joints, disturbances due to external sources of field (the currents flowing in the poloidal field coils and the ferromagnetic inserts of ITER), deviations from ideal geometry, toroidal field variations, calibration, noise and integration drift.
The proposed methods are applied to the measurement error of the CER, in particular in its high and low operating ranges, as prescribed by the ITER system design description documents, and during transients, which highlight the large time constant related to the shielding of the vacuum vessel.
The analyses presented in the paper show that the design of the CER diagnostic is capable of achieving the requisite performance as needed for the operation of the ITER machine. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/1741-4326/aa86fdAdditional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Fusion
- Journal Volume
- 57
- Journal Issue
- 12
- Journal Page Range
- [21 p.]
- ISSN
- 0029-5515
- CODEN
- NUFUAU
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51089845
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ERRORS; ITER TOKAMAK; ROGOWSKI COIL; SENSORS; SIMULATION; STANDARD MODEL
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; FIELD THEORIES; GRAND UNIFIED THEORY; MATHEMATICAL MODELS; PARTICLE MODELS; QUANTUM FIELD THEORY; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; UNIFIED GAUGE MODELS