On line neutron flux mapping in fuel coolant channels of a research reactor
Résumé
This work deals with the on-line neutron flux mapping of the OPAL research reactor. A specific irradiation device has been set up to investigate fuel coolant channels using subminiature fission chambers to get thermal neutron flux profiles. Experimental results are compared to first neutronic calculations and show good agreement (C/E ∼0.97).
Mots clés
on-line neutron flux mapping
Fuels
fission research reactors
fission reactor cooling
Detectors
Radiation effects
Assembly
neutronic calculations
subminiature fission chambers
research reactor
Inductors
Neutrons
fuel coolant channels
OPAL research reactor
Coolants
neutron flux
on line neutron flux mapping
Campbell mode
fission chamber
instrumentation
nuclear instrumentation
ionizing radiation
radioactivity
Origine | Fichiers produits par l'(les) auteur(s) |
---|