Index Catalog // ScholarsArchive@OSU

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

Creator:: Martsolf, Steven W.
Resource Type:: Masters Thesis
Full Text:: Implementation of a Boron Neutron Capture Therapy Research Facility and Dosimetry Program Abstract approved: A

Epithermal neutron beam design at the Oregon State University TRIGA Mark II reactor (OSTR) based on Monte Carlo methods

Creator:: Tiyapun, Kanokrat
Resource Type:: Masters Thesis
Full Text:: thermal neutron components for boron neutron capture therapy (BNCT). A Monte Carlo neutron calculation

The use of ⁶⁰Co cell survival curves in BNCT research

Creator:: Johnson, Jennifer Elizabeth
Abstract:: The cell survival curve is the only means by which to both qualitatively and quantitatively assess morphologic alterations directly resulting from in vitro irradiation of the cell. A ⁶⁰Co cell survival curve experiment has successfully demonstrated the response of the AtT-20 clone mammalian cell line to the effects of gamma...
Resource Type:: Masters Thesis
Full Text:: was developed boron neutron capture therapy (BNCT), an alternative form of radiation therapy. 2

Resonance capture of neutrons by uranium cylinders

Creator:: Davis, Monte V. (Monte Vincent), 1923-
Resource Type:: Dissertation
Full Text:: neutron population. Neutrons which escape capture at energies above the fast fission threshold are

Radiative capture cross sections for the neutrons in a critical sphere of U-235 metal

Creator:: Byers, Cleo Clifford
Resource Type:: Dissertation
Full Text:: nuclei capture neutron• aad iaataataaeoualy (leaa tlaaa lo-12 aecoacla) ealt •-·raya (11, pp.J87-188

Neutron Capture Cross Sections of Cadmium Isotopes

Creator:: Gicking, Allison
Abstract:: The neutron capture cross sections of ¹⁰⁶Cd, ¹⁰⁸Cd, ¹¹⁰Cd, ¹¹²Cd, ¹¹⁴Cd and ¹¹⁶Cd were determined in the present project. Four different OSU TRIGA reactor facilities were used to produce redundancy in the results and to measure the thermal cross section and resonance integral separately. When the present values were compared...
Resource Type:: Undergraduate Thesis
Full Text:: Microsoft Word - intropages1.pdf Neutron Capture Cross

Use of BC-523a liquid scintillator for simultaneous neutron spectroscopy and gamma counting with the implementation of a neutron history reconstruction algorithm

Creator:: Frey, Wesley D.
Abstract:: Real-time, high efficiency neutron spectroscopy has, historically, been a persistent challenge in the field of radiation detection and, for the most part, has gone unsolved. The most promising method to resolve this challenge, is the boron-capture technique using an organic scintillation system (BC-523a). Detectors that utilize this method possess an...
Resource Type:: Dissertation
Full Text:: ........................................... 13 2.3 The Boron-Gated Neutron (BGN) Capture Method .................. 14 2.3.1 Current

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:: interactions, as well as neutron capture and fission reactions. These cross sections are used for nuclear

Retrospective thermal neutron fluence determination using lithium-ion mobile telephone batteries

Creator:: Dorrell, Nick J.
Abstract:: Fortuitous dosimeters are radiosensitive objects carried by an individual who was exposed to radiation. These objects can be analyzed some time after exposure and the results can be used to aid in calculating radiation fields and doses received by individuals. Items that make good fortuitous dosimeters are those that are...
Resource Type:: Masters Thesis
Full Text:: . Boron is commonly used in thermal neutron detectors because of the large cross section of the 10B(n,α

Monte Carlo model of a capture gamma ray analyzer for a seafloor core sample

Creator:: Almasoumi, Abdullah Muhammad Sultan
Abstract:: Of great benefit, but not limited to seafloor mineral exploration, is a technique that fairly rapidly determines the composition of a drilled vibracore (in a time comparable to the time involved in obtaining the core). The rapid assessment is desired to predict whether a given region warrants further exploration by...
Resource Type:: Dissertation
Full Text:: by coring. A proposed monitoring system, based on neutron capture gamma ray analysis, consists of

ScholarsArchive@OSU

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

Epithermal neutron beam design at the Oregon State University TRIGA Mark II reactor (OSTR) based on Monte Carlo methods

The use of ⁶⁰Co cell survival curves in BNCT research

Resonance capture of neutrons by uranium cylinders

Radiative capture cross sections for the neutrons in a critical sphere of U-235 metal

Neutron Capture Cross Sections of Cadmium Isotopes

Use of BC-523a liquid scintillator for simultaneous neutron spectroscopy and gamma counting with the implementation of a neutron history reconstruction algorithm

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

Retrospective thermal neutron fluence determination using lithium-ion mobile telephone batteries

Monte Carlo model of a capture gamma ray analyzer for a seafloor core sample

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