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NTP-ERSN verification with C5G7 1D extension benchmark and GUI development
Lahdour, M.,El Bardouni, T.,El Hajjaji, O.,Chakir, E.,Mohammed, M.,Al Zain, Jamal,Ziani, H. Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.4
NTP-ERSN is a package developed for solving the multigroup form of the discrete ordinates, characteristics and collision probability of the Boltzmann transport equation in one-dimensional cartesian geometry, by combining pin cells. In this work, C5G7 MOX benchmark is used to verify the accuracy and efficiency of NTP-ERSN package, by treating reactor core problems without spatial homogenization. This benchmark requires solutions in the form of normalized pin powers as well as the vectors and the eigenvalue. All NTP-ERSN simulations are carried out with appropriate spatial and angular approximations. A good agreement between NTP-ERSN results with those obtained with OpenMC calculation code for seven energy groups. In addition, our studies about angular and mesh refinements are carried out to produce better quality solution. Moreover, NTP-ERSN GUI has also been updated and adapted to python 3 programming language.
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