The present paper focuses on the modeling of the CROCUS reactor with the French MORET 5 continuous energy code and compares k_eff, anti-reactivity effects (variation of k_eff normalized to k_eff due to the insertion of an absorber), sensitivity coefficients and kinetics parameters with those provided by other reference codes. The aim is mainly to extend the experimental validation/verification database of the MORET 5 code to use reactor physics applications. A suite of about 1400 benchmarks is already available for criticality but only a few are dedicated to reactor physics applications. The CROCUS reactor configurations therefore constitute an opportunity to test and improve the implementation of kinetics parameters and sensitivity coefficients in the code and make a verification of these physical quantities through the comparison with other codes such as MCNP. Moreover, it offers the opportunity to quantify the effect of nuclear data processing through the use of two different data processing codes.

本文着重于使用法国MORET 5连续能级代码对CROCUS反应堆进行建模，并比较了k _eff和抗反应性效应（将k _eff的变化归一化为k _eff（由于插入了一个吸收器），灵敏度系数和动力学参数，以及其他参考代码提供的参数。目的主要是扩展MORET 5代码的实验验证/验证数据库，以使用反应堆物理应用程序。大约有1400个基准测试套件已经可以提供关键性测试，但是只有少数几个专门用于反应堆物理应用。因此，CROCUS反应堆配置提供了一个机会来测试和改进代码中动力学参数和灵敏度系数的实现，并通过与其他代码（例如MCNP）进行比较来验证这些物理量。此外，它还提供了通过使用两种不同的数据处理代码来量化核数据处理效果的机会。