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Filtering by: Alternative title ssim Focus on Forestry at Oregon State University Remove constraint Alternative title ssim: Focus on Forestry at Oregon State University Advisor Palmer, Todd S. Remove constraint Advisor: Palmer, Todd S. Rights Statement In Copyright Remove constraint Rights Statement: In Copyright

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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
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
Application of a Modified Microdosimetric-Kinetic Model to Analyze Cell Killing in Determination of the Optimal Particle for Light Ion Therapy

Creator:

Butkus, Michael P.

Abstract:

Ion therapy has long been investigated as a potential modality to improve cancer treatments beyond what is currently feasible with photon irradiations. Ions offer both a physical and biological advantage over photons. The physical advantages are well understood, ions deposit their maximum dose at defined penetration depths, allowing for minimal...

Resource Type:

Dissertation

Full Text:

will become part of the permanent collection of Oregon State University libraries. My signature below
Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Creator:

Tamashiro, Aaron S.

Abstract:

During the past few decades, the U.S. Department of Energy (DOE) has made significant investments to improve nuclear data libraries, as the quality of this data impacts nearly all analyses of nuclear systems. Nuclear fission product yields are one component of these libraries, and are important for the analysis of...

Resource Type:

Masters Thesis

Full Text:

Oregon State University in partial fulfillment of the requirements for the degree of Master of

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Academic Affiliation

Nuclear Science and Engineering18
Nuclear Engineering and Radiation Health Physics12
Nuclear Engineering4

Advisor

Palmer, Todd S.[remove]35
Greaney, P. Alex1
Palmer, Camille J.1

Commencement Year

Commencement Year range begin – Commencement Year range end

Current results range from 2001 to 2023

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Committee Member

Woods, Brian7
Klein, Andrew C.6
Krane, Kenneth S.5
Palmer, Camille5
Peszynska, Malgorzata4
more Committee Members »

Creator

Keppen, Jackson D.2
Lam, Adam Q.2
Somasundaram, Elanchezhian2
Woods, Douglas N.2
Alberti, Anthony L.1
more Creators »

Contributor

Palmer, Todd S.1
Rising, Michael S.1

Date

Date range begin – Date range end

Current results range from 2000 to 2023

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Decade

2020-20297
2010-201919
2000-20099

Degree Field

Nuclear Engineering33
Medical Physics2

Degree Level

Master's21
Doctoral13
Bachelor's1

Degree Name

Master of Science (M.S.)21
Doctor of Philosophy (Ph.D.)13
Honors Bachelor of Science (H.B.S.)1

File Format

application/pdf1

Language

English [eng]35

License

All rights reserved32

Non-Academic Affiliation

Oregon State University. Graduate School19
Oregon State University. Honors College1

Peer Reviewed

No33

Resource Type

Masters Thesis21
Dissertation13
Honors College Thesis1

Rights Statement

In Copyright[remove]35

Subject

Monte Carlo method4
Radiative transfer -- Mathematical models4
Antineutrinos3
Actinide elements1
Biological models1
more Subjects »

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