tailieunhanh - Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments, and its operating principle. | Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor EPJ Nuclear Sci. Technol. 6 9 2020 Nuclear Sciences c A. Laureau et al. published by EDP Sciences 2020 amp Technologies https epjn 2020004 Available online at https REGULAR ARTICLE Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor Axel Laureau 1 Vincent Lamirand 1 2 Dimitri Rochman 2 and Andreas Pautz 3 1 Laboratory for Reactor Physics and Systems behaviour LRS Ecole Polytechnique F ed erale de Lausanne EPFL 1015 Lausanne Switzerland 2 Laboratory for Reactor Physics and Thermal Hydraulics LRT Paul Scherrer Institut PSI 5232 Villigen Switzerland 3 Nuclear Energy and Safety Research Division NES Paul Scherrer Institut PSI 5232 Villigen Switzerland Received 2 September 2019 Accepted 16 January 2020 Abstract. The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments and its operating principle. Two acceleration techniques have been implemented in the Serpent2 code to perform a Total Monte Carlo uncertainty propagation using variance reduction and correlated sampling technique. Their application to the estimation of the expected reaction rates in dosimeters is also discussed together with the estimation of the impact of the nuisance parameters of aluminium used in the experiment structures. 1 Introduction discrepancy between these different random files is of around 5 30 at high energy bottom-right and may Numerous integral experiments intend to improve the be locally very important near resonances due to the knowledge on the nuclear data and their associated uncer- uncertainty on the energy position of these resonances tainty. Such experiments can be employed to validate middle . the present nuclear .

• Năng lượng
• PETALE experimental programme
• Stainless steel nuclear data
• Total Monte Carlo
• Euro pean Pressurized Reactor
• Propagation of nuclear data
• Nuclear data uncertainty propagation
• Typical pwr fuel assembly with burnup
• The OECD Nuclear Energy Agency UAM
• The Monte Carlo transport
• Burnup code SERPENT
• Expert working group
• Propagation of nuclear data uncertainties for pwr core analysis
• Pwr core analysis
• Bounding estimates in safety margins
• Design and Acceptance Criteria
• Nuclear data application
• Correlated sampling technique
• Monte Carlo simulation
• Total Monte Carlo approach
• CROCUS zero power light water reactor
• Traditional adjoint method
• Impact of ND
• Impact of correlations
• Evaluation of nuclear data
• Material testing reactors
• NEA Nuclear Data Sensitivity Tool
• Half Monte Carlo method
• Uncertainty propagation techniques
• Total Monte Carlo sampling process
• Scenario studies simulate
• Decision making support
• Reactor fleet evolution
• Fuel management options
• Artificial neural network