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Conference Papers Year : 2014

On line neutron flux mapping in fuel coolant channels of a research reactor

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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).
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Dates and versions

cea-01822353 , version 1 (25-06-2018)

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L. Barbot, C. Domergue, J.-F. Villard, C. Destouches, G. Braoudakis, et al.. On line neutron flux mapping in fuel coolant channels of a research reactor. 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), Jun 2013, Marseille, France. ⟨10.1109/ANIMMA.2013.6727951⟩. ⟨cea-01822353⟩
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