Mohamed Mira is a Ph.D. Student in the Radiation and Nuclear Systems Laboratory (ERSN) at the Department of Nuclear Physics, Abdelmalek Essaâdi University, Faculty of Science, Tetouan, Morocco.
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Papers by Mohamed MIRA
G4XRTube: A Geant4-based Monte Carlo application for X-ray tube simulation
Exploiting nuclear waste transuranic (TRU) inventories could be the promising key to developing r... more Exploiting nuclear waste transuranic (TRU) inventories could be the promising key to developing reliable, clean, and sustainable nuclear energy. Towards this objective, different strategies are being considered, and one of the most effective strategies is the development of advanced fuels based on TRU nuclides. In this paper, a novel advanced TRU-based fuel is proposed and investigated as an alternative to the traditional fuel U-ZrH 1.65 for the existing Moroccan research reactor TRIGA Mark II. The TRU nuclides used were derived from a typical 60 GWd/ton PWR-UOX reactor's spent nuclear fuel (SNF) after one use and five years of storage. Before any new fuel loading, several studies must be performed. Hence, The current study focused on the neutronic fuel burnup point of view. MCNP6.2 stochastic code with its burn capability, CINDER90, was used to perform the calculations. In order to get a comprehensive view of the fuel conversion, analyses were performed for the reactor with the traditional fuel U-ZrH 1.65 , and the results were used as the basis for comparative studies of the reactor with the proposed TRU-based fuel. According to the findings, using TRU-based fuel has numerous advantages over traditional fuel U-ZrH 1.65 , such as long lifetime operation, better reactivity control, and low production of some biological hazardous fission products (short-lived fission products, 90 Sr, and 99 Tc). Furthermore, the fuel has highly significant plutonium (Pu) and minor actinides (MAs) burning ratios of about 95.1% and 92.5%, respectively. The results indicate a practical fuel option for the near future, which could be the first step towards using TRU nuclides in existing TRIGA-type reactors.
This work uses the Characteristics Methods (MOC) implemented in the lattice DRAGON5 code to analy... more This work uses the Characteristics Methods (MOC) implemented in the lattice DRAGON5 code to analyze the 2D C5G7 MOX Benchmark. This method was performed using the MCCGT: module of DRAGON5, this module includes parameters that affect the results. So, a sensitivity study was necessary to find the optimum parameters. The eigenvalues calculated by DRAGON5 code agree well with the reference Monte Carlo code MCNP, and also with the OpenMC code with a percent error of just 0.001% and 0.004% respectively. Compared to the Monte Carlo code OpenMC, the maximum percentage error of assembly power, the maximum and the average percentage error of pin power are 0.07%, 0.85% and 0.13%, respectively. Based on the accuracy of the results and on the computational cost, the sensitivity study of various MOC parameters reveals that the 2D C5G7 benchmark problem requires: between 16 and 32 for the azimuthal angles, more than 10 cm − 1 for the ray density and 8 × 8 for the special mesh.
This work uses the Characteristics Methods (MOC) implemented in the lattice DRAGON5 code to analy... more This work uses the Characteristics Methods (MOC) implemented in the lattice DRAGON5 code to analyze the 2D C5G7 MOX Benchmark. This method was performed using the MCCGT: module of DRAGON5, this module includes parameters that affect the results. So, a sensitivity study was necessary to find the optimum parameters. The eigenvalues calculated by DRAGON5 code agree well with the reference Monte Carlo code MCNP, and also with the OpenMC code with a percent error of just 0.001% and 0.004% respectively. Compared to the Monte Carlo code OpenMC, the maximum percentage error of assembly power, the maximum and the average percentage error of pin power are 0.07%, 0.85% and 0.13%, respectively. Based on the accuracy of the results and on the computational cost, the sensitivity study of various MOC parameters reveals that the 2D C5G7 benchmark problem requires: between 16 and 32 for the azimuthal angles, more than 10 cm − 1 for the ray density and 8 × 8 for the special mesh.
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Papers by Mohamed MIRA