Browsing Electronic Theses, Dissertations, and Records of Study (2002– ) by Author "Ragusa, Jean C"
Now showing items 21-39 of 39
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Improved Quasi-Static Methods for Time-Dependent Neutron Diffusion and Implementation in Rattlesnake Prince, Zachary Merritt (2017-04-20)Transient reactor simulations are a chronically formidable challenge due to the computational rigor of evaluating the neutron transport equation, as well as its coupling with other physical phenomena. The goal of this ...
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Vaquer, Pablo A (2022-12-15)The purpose of this research is to reduce the runtime and improve the accuracy of deterministic neutron transport simulations. Here, we introduce the coarse-scattering (CS) method, and prove its ability to reduce the ...
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Scott, Logan Michael (2017-08-25)From the initiation of operations in 1959, the Transient Reactor Test (TREAT) facility at Idaho National Laboratories possessed the potential to serve as the foremost transient testing site in the world. From 1959 to 1994, ...
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Barbu, Anthony Petru (2022-04-11)We develop, analyze, and test iterative methods for three kinds of multigroup transport problems: (1) k-eigenvalue neutronics, (2) thermal radiation transport, and (3) problems with “upscattering,” in which particles can ...
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Kumar, Akansha (2013-04-19)The diffusion approximation to the equation of transfer (Boltzmann transport equation) is usually applied to media where scattering dominates the interactions. Diffusion approximation helps in significant savings in terms ...
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German, Peter (2021-06-29)This work presents a model-order reduction approach for parametric multiphysics problems. The developed method utilizes the intrusive Proper Orthogonal Decomposition aided Reduced Basis technique (POD-RB) which builds ...
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Kliewer, John David (2018-04-24)A nonlinear spatial multigrid algorithm was developed and explored as a technique to efficiently solve the nonlinear S2 acceleration equations for SN neutron transport calculations in 1-D slabs. Acceleration of the basic ...
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Hammer, Hans Rüdiger (2017-07-27)In this dissertation we present advances to the nonlinear diffusion acceleration for void regions using second order forms of the transport equation. We consider the weighted least-squares and the self-adjoint angular flux ...
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Mahadevan, Vijay Subramaniam (Texas A&M University, 2007-04-25)Conventional coupling paradigms used nowadays to couple various physics components in reactor analysis problems can be inconsistent in their treatment of the nonlinear terms. This leads to usage of smaller time steps to ...
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Huhn, Quincy Aaron (2022-06-03)Dynamic Mode Decomposition (DMD) is a method by which spatial modes can be extracted from experimental or numerical data sets. DMD can be used as well to obtain a low rank or reduced operator for a physical system by ...
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Chance, Christopher (2014-09-30)COBRA—TF (CTF) was used to simulate the cooling capabilities for two reactor types that undergo different blockage scenarios. One case considered is a pool-type TRIGA reactor in which instrumentation tubes were inserted ...
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Ghaddar, Tarek (2019-11-04)The field of radiation transport studies the distribution of radiation throughout a seven-dimensional phase-space consisting of time, space, energy, and direction. Radiation transport is described by the Boltzmann equation ...
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Prince, Zachary Merritt (2019-07-15)This research explores the application of a reduced order modeling technique known as proper generalized decomposition (PGD) to models commonly employed in nuclear science and engineering. PGD is an a priori reduced order ...
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Wang, Fang (2014-06-26)An inverse problem reconstructs the unknown internal parameters of a subject based on collected data derived synthetically or from real measurements. Inverse problems often lack the well-posedness defined by J. Hadamard; ...
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Ghesmati, Arezou (2018-01-18)We propose and implement an automatic hp-adaptive refinement algorithm for the Stokes model problem. In this work, the strategy is based on the earlier work done by Dörfler at al. in 2007 for the Poisson problem. Similar ...
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Reed, Michael Shane (2015-05-04)In this dissertation we detail the development, implementation, and testing of a new cut-cell discretization for the discrete ordinates form of the neutron transport equation. This method provides an alternative to ...
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Garcia, Chad (2014-04-24)The primary fuel used in light water nuclear reactors (LWRs) is uranium dioxide (UO2), which has a low thermal conductivity that causes a large thermal gradient across the fuel pin during operation. One proposed method to ...
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Hansel, Joshua Edmund (2013-04-11)A steady-state, single phase subchannel solver was created for the purpose of integration into a multi-physics nuclear fuel performance code. Since applications of such a code include full nuclear reactor core flow simulation, ...
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Schafer, Charles Robert (2019-03-04)Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code with multi-core parallel simulation functionality developed by Los Alamos National Laboratory and is widely used in nuclear ...