ITER Neutral Beam Injectors (NBIs) need to be shielded from the relatively strong stray magnetic field generated by the Poloidal Field Coils of the Tokamak. For this reason both the Heating Neutral Beams (HNB) and the Diagnostic Neutral Beam (DNB) will be provided with a Passive Magnetic Shield and with a system of Active Correction and Compensation Coils (ACCC). The ACCC will operate in feedback control and thus require the measurement of magnetic field inside the NBI vessel, i.e. in an environment subjected to the neutron flux coming from the Tokamak. To this purpose, magnetic sensors which are robust, radiation hard, drift-immune and remote-handling compatible are required. Flux-gate magnetic sensors are a good candidate for this task, but commercial sensors of this kind have typically a limited measured range (below 0.1 mT). The feasibility of a flux-gate sensor for the ITER NBI has been studied by developing a numerical model which includes magnetic core hysteresis, and which demonstrated that, by suitable choice of the core magnetic properties and geometry, it is possible to increase the measurement range by at least 2 orders of magnitude. On this basis, a flux-gate sensor prototype has been realized at Consorzio RFX. Experimental tests carried out so far have demonstrated that the measurement range can be increased to ∼10 mT with acceptable accuracy and frequency bandwidth.
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Materials Science(all)
- Civil and Structural Engineering
- Mechanical Engineering
Chitarin, G., Aprile, D., Brombin, M., Marconato, N., & Svensson, L. (2017). Feasibility study of a flux-gate magnetic field sensor suitable for ITER neutral beam injectors. Fusion Engineering and Design, 123, 412 - 416. https://doi.org/10.1016/j.fusengdes.2017.03.080