Optimization of Swiss used nuclear fuel canister for final repository: Homogeneous vs. mixed loading

Rochman, D.; Vasiliev, A.; Ferroukhi, H.; Pecchia, M.

doi:10.1016/j.anucene.2020.107756

Cited by 4 publications

(1 citation statement)

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“…For the present analysis, the irradiation history for this assembly is not extracted from the ARIANE report, but directly from the PSI database called CMSYS. Such database is normally used for core licensing calculations for the Swiss regulator, and contains all detailed information regarding reactor cycle operations and conditions, necessary for CASMO5 and SIMULATE simulations; interested readers can find more information in references [10][11][12][13][14][15][16][17]. Generally, the PSI database contains a more detailed irradiation history compared to the ARIANE report, with variations of boron concentrations and temperatures at every irradiation step.…”

Section: Samples Assembly and Irradiation Historymentioning

confidence: 99%

Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat

Rochman

Vasiliev

Ferroukhi

et al. 2021

EPJ Nuclear Sci. Technol.

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The Mixed Oxide samples (MOX) ARIANE Post Irradiation Examination samples BM1 and BM3 have been analyzed in this work, based on various two- and three-dimensional models. Calculated and measured nuclide inventories are compared based on CASMO5, SIMULATE and SNF simulations, and calculated values for the decay heat of the assembly containing the samples are also provided. For uncertainty propagation, the covariance information from three different nuclear data libraries are used. Uncertainties from manufacturing tolerances and operating conditions are also considered. The results from these two samples are compared with the ones from two UO2 samples, namely GU1 and GU3, also from the ARIANE program, applying the same calculation scheme and uncertainty assumptions. It is shown that a two-dimensional assembly model provides better agreement with the measurements than a two-dimensional single pin model, and that the full core three-dimensional model provides similar results compared to the assembly model, although no 148Nd normalization is applied for the full core model. For the MOX assembly decay heat, as expected, heavy actinides have a higher contribution compared to the cases with the UO2 samples; additionally, decay heat uncertainties are moderately smaller in the case of the MOX assembly.

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