DocumentCode
3652108
Title
On line neutron flux mapping in fuel coolant channels of a research reactor
Author
Loic Barbot;Christophe Domergue;Jean-Francois Villard;Christophe Destouches;George Braoudakis;David Wassink;Bradley Sinclair;John C. Osborn; Huayou Wu;Christophe Blandin;Mathieu Thevenin;Gwenole Corre;Stephane Normand
Author_Institution
DEN, DER, Instrum., Sensors &
fYear
2013
fDate
6/1/2013 12:00:00 AM
Firstpage
1
Lastpage
5
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
"Neutrons","Inductors","Fuels","Coolants","Assembly","Radiation effects","Detectors"
Publisher
ieee
Conference_Titel
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2013 3rd International Conference on
Type
conf
DOI
10.1109/ANIMMA.2013.6727951
Filename
6727951
Link To Document