Speaker
Description
Accurate estimation of spent nuclear fuel (SNF) nuclide inventory is of great importance for safety aspects of the back-end of the nuclear fuel cycle. In this regard, it is necessary to assess the impact of nuclear data uncertainties on SNF inventories.
A PWR UO2 post-irradiation-examination (PIE) fuel rod sample for which experimental data are available has been studied within the Sub-Groups 7[1], 10[2] and 15[3] of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency (NEA).
Within this framework, ASNR has performed CASMO-5 [4] calculations on this sample using ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries and has first analysed the Calculation-over-Experiment (C/E-1) values for nuclides mainly important in burnup credit methodologies [5]. In a second step, the nuclear data uncertainties have been propagated to the concentrations results, and their impact on the C/E-1 biases has been studied. The total nuclear data uncertainty, as well as the individual contributions of the cross sections and nu-bar, fission yields, and decay data, have been propagated using the random sampling method of CASMO, using the ENDF/B-VIII.0 nuclear data covariances. The results are summarized and discussed in this paper.
[1] NEA (2023), WPNCS, SG7, Synthesis of the subgroup 7 activities: Specification of a benchmark on Sensitivity / Uncertainty Analysis for PWR UOx spent nuclear fuel
[2] WPNCS, SG10, Synthesis of the subgroup 10 activities: Phase I of Nuclear data uncertainties quantification on spent fuel inventory – OECD Pending publication
[3] WPNCS, SG15, Synthesis of the subgroup 15 activities: Phase II of Nuclear data uncertainties quantification on spent fuel inventory – OECD Pending publication
[4] J. Rhodes, K. Smith, and D. Lee, “CASMO-5 Development and Applications,” Proc. Int. Conf. on Advances in Nuclear Analysis and Simulation (PHYSOR 2006), Vancouver, BC, Canada, Sept. 10-14 (2006)
[5] Jutier, Ludyvine & Riffard, C. & Santamarina, Alain & Guillou, E. & Grassi, Gabriele & Lecarpentier, D. & Lauvaud, F. & Coulaud, A. & Hampartzounian, M. & Tardy, M. & Kitsos, S.. (2015). Burnup Credit Implementation for PWR UOX Used Fuel Assemblies in France: From Study to Practical Experience. Nuclear Science and Engineering. 181. 10.13182/NSE14-51.
| Session | Uncertainties and Covariance Matrices (methodology and reactor calculation impacts) |
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