DocumentCode
1762119
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
Volume
62
Issue
2
fYear
2015
fDate
42095
Firstpage
415
Lastpage
419
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;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2015.2396637
Filename
7058454
Link To Document