Comparison of thermal neutron flux measured by uranium 235 fission chamber and rhodium self-powered neutron detector in MTR

@article{Fourmentel2013ComparisonOT,
  title={Comparison of thermal neutron flux measured by uranium 235 fission chamber and rhodium self-powered neutron detector in MTR},
  author={Damien Fourmentel and Philippe Filliatre and Loic Barbot and J. F. Villard and A. Lyoussi and B. Geslot and Hubert Carcreff and J-Y. Malo and Christelle Reynard-Carette},
  journal={2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)},
  year={2013},
  pages={1-7}
}
Thermal neutron flux is one of the most important nuclear parameter to be measured on-line in Material Testing Reactors (MTRs). In particular two types of sensors with different physical operating principles are commonly used: self-powered neutron detectors (SPND) and fission chambers with uranium 235 coating. This work aims to compare on one hand the thermal neutron flux evaluation given by these two types of sensors and on the other hand to compare these evaluations with activation dosimeter… CONTINUE READING