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Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations

Abstract : The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high-temperature fission chambers installed in the reactor vessel and capable of operating over a wide-range neutron flux. The definition of such a system is presented and the technological solutions are justified with the use of simulation and experimental results.
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Submitted on : Monday, March 30, 2020 - 10:57:00 PM
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C. Jammes, P. Filliatre, Zs. Elter, V. Verma, G. de Izarra, et al.. Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations. 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Apr 2015, Lisbon, Portugal. ⟨10.1109/ANIMMA.2015.7465647⟩. ⟨hal-01282997⟩

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