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Full-Text Articles in Nuclear Engineering
Monte Carlo Perturbation Analysis Of Dimension And Density Variations Of The Annular Core Research Reactor Model Fuel, Karissa Currie
Monte Carlo Perturbation Analysis Of Dimension And Density Variations Of The Annular Core Research Reactor Model Fuel, Karissa Currie
Nuclear Engineering ETDs
This thesis assesses sources of uncertainty in the neutron energy spectrum of the Annular Core Research Reactor (ACRR) Monte Carlo N-Particle Transport Code (MCNP) model. Uncertainty evaluations have been performed on the ACRR core but were computationally intensive and could not isolate the uncertainties associated with discrete sources. Monte Carlo Perturbation Theory (MCPT) is used in MCNP to calculate 640-group neutron energy fluences and their associated uncertainties [1]. To understand the uncertainties associated with only the UO2-BeO fuel, perturbations in densities and dimensions were evaluated. A 640 by 640 covariance and correlation matrices were produced and compared to …
Monte Carlo Perturbation Analysis Of Fuel Temperature Variations In The Mcnp Model Of The Annular Core Research Reactor, Melissa Andrea Moreno
Monte Carlo Perturbation Analysis Of Fuel Temperature Variations In The Mcnp Model Of The Annular Core Research Reactor, Melissa Andrea Moreno
Nuclear Engineering ETDs
The Annular Core Research Reactor (ACRR) Monte Carlo N-Particle (MCNP) model is used for a variety of computational calculations ranging from reactor kinetics metrics to safety analyses. To understand the dominant source of uncertainty within the model, perturbations in temperature were applied to individual ACRR MCNP fuel rods. Assigning random temperatures, selected uniformly, from the operational temperature ranges of the fuel enables a study of uncertainty effects based on temperature variations. Stochastic mixing was used to blend the cross-sections of the desired temperatures using the MCNP continuous and Thermal Neutron Scattering Treatment (S(α,β)) libraries in ENDF/B-VII.1. The uncertainty quantification process …
The Inverse Kinetics Method And Its Application To The Annular Core Research Reactor, Thomas A. Ball
The Inverse Kinetics Method And Its Application To The Annular Core Research Reactor, Thomas A. Ball
Nuclear Engineering ETDs
The inverse kinetics method, is a method to calculate a reactor’s reactivity profile from its power profile. In this thesis, the reactivity profile corresponding to pulse operations of the Annular Core Research Reactor (ACRR) was sought. Of specific interest was the shutdown reactivity of the reactor following the pulse. This required accounting for delayed beryllium photoneutrons that are present in the ACRR in addition to U-235 delayed neutron precursors. The power profiles of the pulses were experimentally measured using a diamond photoconductive detector (PCD). Using the inverse kinetics equation, a computer code was written to numerically calculate the reactivity corresponding …