MCNP5 calculations compared to experimental measurements in CEA-MINERVE reactor

The paper describes the calculation performed by INR-Pitesti of a benchmark problem proposed by CEA Cadarache consisting in experimental measurements in MINERVE reactor. The purpose of the problem concerned the qualification of Valmont fuel pin (U-Mo-Al) designed for radio-pharmaceutical sources production. First, an MCNP model for the MINERVE facility was created. The model was then used to obtain results to compare with safety parameters and experimental physics measurements such as:control rods worth, Valmont pin reactivity worth, axial fission rate distribution in some of the experimental zone pins including Valmont, spectral indices and U-238 conversion ratio. A description of the MCNP model is provided in the paper together with the results obtained against the experimental results.