Title :
On Line Neutron Flux Mapping in Fuel Coolant Channels of a Research Reactor
Author :
Barbot, Loic ; Domergue, Christophe ; Villard, Jean-Francois ; Destouches, Christophe ; Braoudakis, George ; Wassink, David ; Sinclair, Bradley ; Osborn, John C. ; Huayou Wu ; Blandin, Christophe ; Thevenin, Mathieu ; Corre, Gwenole ; Normand, Stephane
Author_Institution :
Sensors & Dosimetry Lab., CEA, Cadarache, France
Abstract :
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).
Keywords :
fission reactor cooling; fission research reactors; neutron flux; OPAL research reactor; fuel coolant channels; neutronic calculations; on line neutron flux mapping; subminiature fission chambers; Assembly; Coolants; Detectors; Fuels; Inductors; Neutrons; Radiation effects; Campbell mode; fission chamber; on-line neutron flux mapping; research reactor;
Journal_Title :
Nuclear Science, IEEE Transactions on
DOI :
10.1109/TNS.2015.2396637
