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 hightemperature 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.
Type de document :
Communication dans un congrès
4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications , Apr 2015, Lisbon, Portugal
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https://hal-centralesupelec.archives-ouvertes.fr/hal-01282997
Contributeur : Emmanuel Odic <>
Soumis le : vendredi 4 mars 2016 - 17:13:47
Dernière modification le : lundi 1 octobre 2018 - 16:03:24

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  • HAL Id : hal-01282997, version 1

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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 , Apr 2015, Lisbon, Portugal. 〈hal-01282997〉

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