Browsing by Author "Blandin, C"

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    On line neutron flux mapping in fuel coolant channels of a research reactor
    (IEEE, 2014-01-30) Barbot, L; Domergue, C; Villard, JF; Destouches, C; Braoudakis, G; Wassink, D; Sinclair, B; Osborn, JC; Wu, H; Blandin, C; Thévenin, M; Corre, G; Normand, S
    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). © 2022 IEEE