On line neutron flux mapping in fuel coolant channels of a research reactor
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IEEE
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). © 2022 IEEE
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Barbot, L., Domergue, C., Villard, J. F., Destouches, C., Braoudakis, G., Wassink, D., Sinclair, B., Osborn, J. C., Wu, H., Blandin, C., Thévenin, M., Corre, G., & Normand, S. (2013). On line neutron flux mapping in fuel coolant channels of a research reactor. Paper presented at the 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), 23-27 June 2013, Marseille, France. In IEEE Transactions on Nuclear Science 62(2). doi:10.1109/ANIMMA.2013.6727951