In order to study the sensitivity and the uncertainty of the Moroccan research reactor TRIGA Mark II, a model of this reactor has been developed in our ERSN laboratory for use with the N-Particle MCNP Monte Carlo transport codes (version 6). In this article, the sensitivities of the effective multiplication factor of this reactor are evaluated using the ENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0 libraries and in 44 energy groups, 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 for the 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 pcm respectively for the reactions U₂₃₅(n, f), U₂₃₅(n$\overline{\nu }$) and H₁(n, γ). On the other hand, these differences are very 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 spectra present two peaks (thermal and fission) around the energies 0.05 eV and 1 MeV.

为了研究摩洛哥研究反应堆 TRIGA Mark II 的敏感性和不确定性，我们的 ERSN 实验室开发了该反应堆的模型，用于 N-Particle MCNP Monte Carlo 传输代码（第 6 版）。在本文中，使用 ENDF/B-VII.0、ENDF/B-VII.1 和 JENDL-4.0 库和在 44 个能量组中评估了该反应器的有效倍增因子的敏感性，对于横截面燃料（U-235 和 U-238）和慢化剂（H-1 和 O-16）。然而，核数据不确定性的量化是使用核代码 NJOY99 进行的，用于协方差矩阵的生成和处理。一方面，使用 ENDFB-VII.1 和 JENDL4.0 评估计算的最高不确定性偏差对于反应 U 分别为 2275、386 和 330 pcm₂₃₅ (n, f ), U ₂₃₅ (n$\overline{\nu }$) 和 H ₁ (n, γ)。另一方面，对于 O-16 和 U-238 的中子反应，这些差异非常小。关于中子光谱，在 CT 中平面，它们对于三个评估（ENDF/B-VII.0、ENDF/B-VII.1 和 JENDL-4.0）非常接近。这些光谱在能量 0.05 eV 和 1 MeV 附近呈现出两个峰（热峰和裂变峰）。