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A. Arectout,I. Zidouh,Y. Sadeq,M. Azougagh,B. Maroufi,E. Chakir,H. Boukhal 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.1
This work aims to establish some X-ray qualities recommended by the International Standard Organization(ISO) using the half-value layer (HVL) and Hp(10) dosimetry approaches. The HVL values of thefollowing qualities N-60, N-80, N-100, N-150 and N-250 were determined using various attenuationlayers. The obtained results were compared to those of reference X-ray beam qualities and a goodagreement was found (difference less than 5% for all qualities). The GAMOS (Geant4-based Architecturefor Medicine-Oriented Simulations) radiation transport Monte Carlo toolkit was employed to simulatethe production of X-ray spectra. The characteristics HVLs, mean energy and the spectral resolution ofsimulated spectra have been calculated and turned out to be conform to the ISO reference ones (differenceless than the limit allowed by ISO). Furthermore, the conversion coefficients from air kerma topersonal dose equivalent for simulated and measured spectra were fairly similar (the maximum differenceless than 4.2%)
M. Makhloul,H. Boukhal,E. Chakir,T. El Bardouni,M. Lahdour,M. Kaddour,Abdulaziz Ahmed,A. Arectout,H. El Yaakoubi 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.2
In order to study the sensitivity and the uncertainty of the Moroccan research reactor TRIGA Mark II, amodel of this reactor has been developed in our ERSN laboratory for use with the N-Particle MCNP MonteCarlo transport codes (version 6). In this article, the sensitivities of the effective multiplication factor ofthis reactor are evaluated using the ENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0 libraries and in 44 energygroups, for the cross sections of the fuel (U-235 and U-238) and the moderator (H-1 and O-16). However,the quantification of the uncertainty of the nuclear data is performed using the nuclear code NJOY99 forthe generation and processing of covariance matrices. On the one hand, the highest uncertainty deviations, calculated using the ENDFB-VII.1 and JENDL4.0 evaluations, are 2275, 386 and 330 pcmrespectively for the reactions U235(n, f), U235(nn) and H1(n, g). On the other hand, these differences arevery small for the neutron reactions of O-16 and U-238. Regarding the neutron spectra, in CT-mid plane,they are very close for the three evaluations (ENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0). These spectrapresent two peaks (thermal and fission) around the energies 0.05 eV and 1 MeV