2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMM 2013
DOI: 10.1109/animma.2013.6727951
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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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Cited by 5 publications
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“…As presented in [9,10], MONACO system performances are consistent with other high standard acquisition system in pulse counting mode and neutron flux estimation by simulation using MCNP5 v1.6. with an average C/E ratio 0.97 -5% dispersion.…”
Section: Experimental Design Validationsupporting
confidence: 52%
“…As presented in [9,10], MONACO system performances are consistent with other high standard acquisition system in pulse counting mode and neutron flux estimation by simulation using MCNP5 v1.6. with an average C/E ratio 0.97 -5% dispersion.…”
Section: Experimental Design Validationsupporting
confidence: 52%