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

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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https://hal-cea.archives-ouvertes.fr/cea-01822353
Contributor : Léna Le Roy Connect in order to contact the contributor
Submitted on : Monday, June 25, 2018 - 7:58:48 AM
Last modification on : Friday, June 25, 2021 - 10:00:02 AM

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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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