On line neutron flux mapping in fuel coolant channels of a research reactor
- Barbot, L.
- Domergue, C.
- Villard, J.-F.
- Destouches, C.
- Braoudakis, G.
- Wassink, D.
- Sinclair, B.
- Osborn, J.C.
- Wu, H.
- Blandin, C.
- Thevenin, M.
- Corre, G.
- Normand, S.
Publication date
June 2013
DOI Publisher
Institute of Electrical and Electronics Engineers (IEEE) Citation count (estimate)
3Abstract
Conference of 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications, ANIMMA 2013 ; Conference Code:102802International audienceThis 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)
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