Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations

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概要

• 論文の詳細を見る

• In this paper, we present an uncertainty methodology based on a statistical approach, for assessing uncertainties in lattice code predictions of fuel composition changes with burnup due to uncertainties in the fuel geometric configuration, initial enrichment, and depletion conditions. The methodology has been applied to depletion calculations with CASMO-4 and experimental data from the ARIANE Programme to estimate the calculation uncertainties in nuclide concentration and other neutronic parameters at any time during the irradiation history. Results have shown that important information on the quality of the code’s predictions can be obtained by analyzing the comparison of the code’s estimates and their associated uncertainties, in the form of tolerance intervals, with experimental data and their reported errors.

• 一般社団法人 日本原子力学会の論文
• 2007-06-25

著者

• Chawla Rakesh

  Paul Scherrer Institute Villigen Psi

• Chawla Rakesh

  Paul Scherrer Institut

• ZIMMERMANN Martin

  Paul Scherrer Institut

• Zimmermann Martin

  Paul Scherrer Institute Villigen Psi

• MACIAN Rafael

  Paul Scherrer Institute, Villigen PSI

• Macian Rafael

  Paul Scherrer Institute Villigen Psi

• Macian Rafael

  Paul Scherrer Institut

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• Comparisons of Deterministic Neutronic Calculations with Monte Carlo Results for an Advanced BWR Fuel Assembly with Hafnium Control Blades
• The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility
• Investigation of ADS-Type Heterogeneities in the MUSE4 Critical Configuration
• Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients
• Interpretation of High-Burnup Fuel Annealing Tests
• Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations
• The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility

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