Abstract
Neutron detection is a relevant topic in the field of nuclear instrumentation. It is at the heart of the concerns for fusion applications (neutron diagnostics, measurements inside the Test Blanket Modules TBM) as well as for fission applications (in-core and ex-core monitoring, neutron mapping or safety applications in research reactors). Moreover, due to the even more harsh conditions of the future experimental reactors such as the Jules Horowitz Reactor (JHR) or International Thermonuclear Experimental Reactor (ITER), neutron detectors need to be adapted to high neutron and γ fluxes, high nuclear heating rates and high temperatures. Consequently, radiation and temperature hardened sensors with fast response, high energy resolution and stability in a mixed neutron and γ environment are required. All these requirements make wide-bandgap semiconductors and, more precisely, Silicon Carbide (SiC) serious candidates due to their intrinsic characteristics in such extreme environments. Thus, since the last decades, SiC-based detectors are developed and studied for neutron detection in various nuclear facilities. In this paper, a SiC-based neutron detector is 3-D designed and studied through thermal and radiation-matter interaction numerical simulations for a future irradiation campaign at the Jožef Stefan Institute TRIGA Mark II research reactor in Slovenia. Firstly, this paper presents the scientific background and issues of our SiC-based detectors. In a second part the 3-D geometry is shown. Thereafter, the 3-D numerical thermal simulation results are reported. Finally, the 3-D numerical radiation/matter interaction simulations results are presented.
Highlights
AND ISSUESIN a nuclear reactor, either for fission or fusion applications, it is crucial to measure key parameters such as neutron and fluxes or nuclear heating rate for a better understanding of the behavior of nuclear fuels or materials subjected to nuclear radiation and for the monitoring of the nuclear facilities
Thanks to the 3-D thermal simulations and 3-D radiation/matter interaction simulations, various conclusions were obtained for a future qualification of the Silicon Carbide (SiC)-based detector in the JSI TRIGA Mark II reactor
For the 3-D numerical thermal simulations, firstly the heat transfer coefficient values calculated by COMSOL are coherent with those estimated by using correlations of the literature
Summary
IN a nuclear reactor, either for fission or fusion applications, it is crucial to measure key parameters such as neutron and fluxes or nuclear heating rate for a better understanding of the behavior of nuclear fuels or materials subjected to nuclear radiation and for the monitoring of the nuclear facilities. The 3-D thermal simulations realized by means of COMSOL Multiphysics finite element code are presented The aim of these thermal simulations is to determine the maximum temperature and the temperature field inside the system and in particular in the SiC-based diode for various boundary conditions and the expected nuclear heating rate range. In order to reduce the calculation time, a simplified system as that implemented for 3-D numerical thermal simulations is used
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