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Science and Technology of Nuclear Installations
Volume 2017, Article ID 5369614, 8 pages
https://doi.org/10.1155/2017/5369614
Research Article

Neutron Flux Monitoring Based on Blind Source Separation Algorithms in Moroccan TRIGA MARK II Reactor

1LPNR, Department of Physics, Faculty of Sciences, Mohammed V University, 1014 RP, Rabat, Morocco
2National Centre for Nuclear Energy, Sciences and Techniques (CNESTEN), 1382 RP, 10001 Rabat, Morocco

Correspondence should be addressed to Hanane Arahmane; moc.liamtoh@1ra_enanah and El-Mehdi Hamzaoui; moc.liamg@idhemleiuoazmah

Received 22 December 2016; Revised 22 February 2017; Accepted 7 March 2017; Published 30 March 2017

Academic Editor: Eugenijus Ušpuras

Copyright © 2017 Hanane Arahmane et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Abstract

We present an overview of fission chamber’s functioning modes, theoretical aspects of the nonnegative matrix factorization methods, and the opportunities that offer neutron data processing in order to achieve neutron flux monitoring tasks. Indeed, it is a part of research project that aimed at applying Blind Source Separation methods for in-core and ex-core neutron flux monitoring while analyzing the outputs of fission chamber. The latter could be used as a key issue for control, fuel management, safety concerns, and material irradiation experiments. The Blind Source Separation methods had been used in many scientific fields such as biomedical engineering and telecommunications. Recently, they were used for gamma spectrometry data processing. The originality of this research work is to apply these powerful methods to process the fission chamber output signals. We illustrated the effectiveness of this tool using simulated fission chamber signals.