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Browsing Theses and Dissertations (Nuclear Engineering and Radiation Health Physics) by Title

Browsing Theses and Dissertations (Nuclear Engineering and Radiation Health Physics) by Title

Now showing items 34-53 of 170

Design and implementation of a boron neutron capture therapy research facility and dosimetry program

Martsolf, Steven W. (1993-05-21)
Design and simulation of a self-powered neutron spectrometer

Kropp, Edward K. (1998-08-12)

A self-powered neutron detector (SPND) is a device that, coupled with a current meter, provides a readout proportional to neutron population. This thesis discusses the design parameters of an array of such devices, the ...
Design and testing of fabric composite heat pipes for space nuclear power applications

Kiestler, William C. (1992-12-16)

Conventional stainless steel - water and ceramic fabric composite water heat pipes have been built and tested. The tests have been conducted to compare the performance characteristics between conventional and fabric co ...
Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters

McCreary, David M. (2000-10-26)

This thesis examines two techniques for measuring two-phase flow parameters in an air/water system using intrusive conductivity probes. Specifically, the theoretical derivation for measuring void fraction and interfaci ...
Design, construction, and characterization of a neutron depth profiling facility at the Oregon State University TRIGA® reactor with an advanced digital spectroscopy system

Robinson, Joshua A. (2012-07-13)

In this work, Neutron Depth Profiling (NDP) analysis capability has been added to the Oregon State University TRIGA® Reactor Prompt Gamma Neutron Activation Analysis Facility (PGNAA). This system has been implemented wit ...
Determination of a calculation bias in the MCNP model of the OSTR

Kitto, Allyson K. (2012-12-05)

Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008, the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a Monte Carlo code that can be used for c ...
Determination of effective doses from radionuclides in the Columbia River sediments

Wu, Renpo (1994-08-25)
Determination of Phoswich detector response using MCNP analysis to enhance Radioxenon measurement

Lopez, Alejandro Uriel (2006-04-27)

As mandated by the Comprehensive Nuclear Test Ban Treaty (CTBT), the United States (US) is involved in the development and deployment of an International Monitoring System (IMS) for monitoring nuclear explosions. The US ...
Determination of the optimum counting geometry for low-energy photon emitting hot particles

Menn, Scott A., 1970- (2001-04-30)
Determination of ⁹⁰Sr/⁹⁰Y contamination using beta-particle spectroscopy with active gamma-ray discrimination

Baik, Seung-Hyuk (1991-08-08)
Determining cross sections for potential medical radioisotopes

Coleman, Joseph W. (2003-06-10)
Determining preliminary remediation goals for contaminated Hanford sites

Hekkala, Darin R. (1996-05-22)

The Hanford nuclear reservation in Washington state was initially created during World War II for the production of plutonium to be used in atomic bombs. A perceived need for a large increase in the number of nuclear w ...
Determining the activity distribution on a radioactive stent using plastic scintillation techniques

Bergman, Joshua J. (2000-06-23)

Re-occlusion of arteries following percutaneous transluminal coronary angioplasty (PTCA) remains a post-operative issue in the treatment of artery blockage. This re-narrowing of the luminal cavity, a condition called r ...
Determining the bioavailability of soil-associated radium using in vitro methodology

Tack, Krystina M. (2006-03-01)

Soil that is contaminated with radioactive elements poses an exposure hazard to those whom may take up temporary or permanent residence on such a site. Of particular interest is the internal exposure from ingestion of ...
Development of a binary mixture gas composition instrument for use in a confined high temperature environment

Cadell, Seth R. (2012-11-28)

With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a division of the field is working to develop the ...
Development of a dose conversion factor from uptakes of Po-210 through smoking using a modified ICRP 30 lung model

Hout, Jason D. (2010-10-11)

A thesis presented on the determination of factors related to deposition, clearance, and dosimetry of the ICRP 30 lung model as related to smoking. Variations in calculations used to determine radiation doses leave a ne ...
Development of a functional prototype of an environmental risk assessment parameter database on the World-Wide Web

Potter, Nathan Kent (1997-08-06)

The goal of the project was to develop a functional prototype of an environmental risk assessment parameter database on the World-Wide Web. The ability to develop a consolidated environmental database has become possib ...
Development of systems analysis program for space reactor studies

Lewis, Bryan R. (1993-06-14)

An overall systems design code was developed to model an advanced in-core thermionic energy conversion based nuclear reactor system for space applications at power levels of 10 to 50 kWe. The purpose of this work was ...
Diffusion of selected radionuclides through Hanford Trench 8 soil material

Schwab, Kristen E. (2003-10-17)

Shallow land burial in vadose zone sediment at the Hanford Site in Washington is being considered for the disposal of Category 3 low-level waste. A series of column experiments were conducted to evaluate and model the ...
Dosimetric verification of respiratory gated radiation therapy for tumors involving the lung

Webb, Lindsey S. (2010-12-01)

As the field of radiation therapy evolves new treatment techniques will be established. An example of an evolving treatment technique is respiratory gated radiation therapy (RGRT). Research and studies have shown that ...