Burnup - PowerPoint PPT Presentation

This study presents a probabilistic approach for solving burnup problems in nuclear transmutations, offering a new method free from the challenges of traditional approaches. It includes an introduction to burnup equations, outlines of the methodology, and the probabilistic method's mathematical form

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Nuclear Data Needs for Spent Fuel Dry Storage and Radioactive Materials Transportation workshop held by US NRC discussed criticality safety, burnup credit, code validation, and organizational aspects in the field. The Division of Spent Fuel Management highlighted transportation and storage regulatio

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A comprehensive overview of reactivity trends in ENDF/B-VIII.0 due to uranium cross-sections and burnup, highlighting differences from ENDF/B-VII.1. Focus areas include loss of reactivity in PWRs, discrepancies in individual nuclide substitution, and updates in U-235 evaluation. Notable changes in U

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When a non-stationary reactor is shut down or its load is reduced to zero, xenon poisoning occurs due to the disruption of dynamic equilibrium between the increase and decrease of 135Xe. This leads to a temporary increase in 135Xe concentration, followed by a decrease as it decays. The reactivity ma

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The content discusses sensitivity analysis in burnup calculations using the Monte Carlo method, exploring uncertainty methods, comparison of adjoint and direct calculations, and sensitivities to initial conditions. It also covers topics such as the total Monte Carlo method, steady state calculations

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Support the EU Member States in improving their nuclear modeling skills through comprehensive nuclear data projects focusing on various aspects such as spent fuel data, reactivity vs. burnup, advanced nuclear concepts, criticality safety, and non-energy applications. Develop the JEFF library to addr

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