Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations
Résumé
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.
Mots clés
Reactor operating
French GEN-IV SFR
Experimental validation
GEN-IV sodium-cooled fast reactor
Reactor vessel
Neutron flux monitoring system
Safety
Temperature sensors
Cascading style sheets
Inductors
Detectors
Monitoring
Neutrons
Neutron flux
Liquid metal fast breeder reactors
Fission reactor instrumentation
Nuclear instrumentation
Origine | Fichiers produits par l'(les) auteur(s) |
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