Index Catalog // ScholarsArchive@OSU

Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

Creator:: Keller, S. Todd
Abstract:: Attila is a state-of-the-art radiation transport based code that is efficient, accurate and straightforward to use. Geometric information is input to the code as CAD drawings. Material property information is input as a cross section library. The user has full control over standard transport options and output reports. In phase...
Resource Type:: Masters Thesis
Full Text:: presented on _January 30, 2007_____ Title: Modeling the Oregon State University TRIGA Reactor Using the

Predicting dose and cell survival distributions for brachytherapy sources

Creator:: Stringham, Michael J.
Abstract:: The focus of this thesis is to determine the biological impact of dose from brachytherapy sources commonly used in cancer treatment. To achieve this goal, the Monte Carlo code PENELOPE was used to simulate point sources of four different isotopes (¹⁰³Pd, ¹²⁵I, ¹³⁷Cs, and ⁹⁰Sr) in an infinite medium of...
Resource Type:: Masters Thesis

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Creator:: Brice, Derek J.
Resource Type:: Masters Thesis
Full Text:: . Todd S. Palmer for giving me the opportunity to complete my degree at Oregon State University and for

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

Creator:: Strohecker, Mark F.
Abstract:: The OSU/APEX thermal hydraulic test facility models the passive safety systems of the Westinghouse AP600 advanced light water reactor design. Numerous experiments have been performed to test these systems, the one of focus here is the station blackout scenario. This experiment simulated the complete loss of AC power to all...
Resource Type:: Masters Thesis
Full Text:: Facility by Mark F. Strohecker A THESIS submitted to Oregon State University in partial

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

Creator:: Woods, Douglas N.
Abstract:: We spatially discretize the Sn transport equation using the high-order (HO) discontinuous finite element method (DFEM) on HO meshes. Previous work provided a proof-of-concept for this spatial discretization method in X-Y geometry. Included in the present work, we derive a spatial discretization for the Sn transport equation in both X-Y...
Resource Type:: Dissertation
Full Text:: DISSERTATION submitted to Oregon State University in partial fulfillment of the requirements for the degree

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

Creator:: Woods, Douglas N.
Abstract:: The high-order finite element S[subscript N] transport equations are solved on several test problems to investigate the behavior of the discretization method on meshes with curved edges in X-Y geometry. Simpler problems ensured the correct implementation of MFEM, the general fi nite element library employed. A convergence study using the...
Resource Type:: Masters Thesis
Full Text:: in the Thick Diffusion Limit by Douglas N. Woods A THESIS submitted to Oregon State University

Design and analysis of a nuclear reactor core for innovative small light water reactors

Creator:: Soldatov, Alexey I.
Abstract:: In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
Resource Type:: Dissertation
Full Text:: remote communities, Oregon State University has proposed the Multi-Application Small Light Water

Analysis of the method of tubes characteristic schemes in the thick diffusive limit

Creator:: Rising, Michael E.
Abstract:: Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport problems. These methods are most often used for neutron transport applications (i.e. lattice physics calculations) where spatial cells are of intermediate optical thickness (O(1) - O(100) mean free paths, depending on the energy group)...
Resource Type:: Masters Thesis
Full Text:: both LLNL and at Oregon State University very worthwhile. In no particular order, I would like to

Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry

Creator:: Hummel, Andrew J.
Abstract:: Reactor modeling is largely limited by the computational time required to perform accurate full core calculations. There are many different methods and techniques employed in different reactor simulation codes, but properly modeling all of the physics that takes place in the system requires extensive computational effort. The Coarse Mesh Finite...
Resource Type:: Masters Thesis
Full Text:: A THESIS submitted to Oregon State University in partial fulfillment of the

Investigation Into the Use of a Lead Slowing Down Spectrometer for Neutron Cross Section Analysis

Creator:: Keppen, Jackson D.
Abstract:: A lead slowing-down spectrometer (LSDS) was modeled in the hopes of beginning a nuclear data development campaign at Oregon State University. An LSDS can be used for neutron interrogation techniques, such as determining isotopic inventory of a sample of unknown components or determining the cross section of a sample of...
Resource Type:: Honors College Thesis
Full Text:: a standard laboratory room within the Radiation Center at Oregon State University [16]. The room is

ScholarsArchive@OSU

Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

Predicting dose and cell survival distributions for brachytherapy sources

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

Design and analysis of a nuclear reactor core for innovative small light water reactors

Analysis of the method of tubes characteristic schemes in the thick diffusive limit

Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry

Investigation Into the Use of a Lead Slowing Down Spectrometer for Neutron Cross Section Analysis

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