The purpose of this research was to develop and test a radiation detector to perform
beta dosimetry and spectroscopy. The detector utilizes plastic scintillator volumes to
produce scintillation light in proportion to the amount of energy deposited in them,
and a large-area avalanche photodiode to convert the light to electrical signals. Pulse
processing electronics transform the electrical signals into a format useful for analysis,
and various software programs are used to analyze the resulting data. The detector
proved capable of measuring dose, as compared to Monte Carlo n-Particle simulations,
to within about 50% or better, depending on geometry and source type. Spectroscopy
results, in conjunction with MCNP-based spectral enhancement methods, proved the
detector capable of recording beta spectra with endpoint energies greater than about
250 keV. The detector shows promise for further development as a portable beta
detector for field use in beta-contaminated areas. / Graduation date: 2005
| Identifer | oai:union.ndltd.org:ORGSU/oai:ir.library.oregonstate.edu:1957/31691 |
| Date | 03 June 2004 |
| Creators | Kriss, Aaron A. |
| Contributors | Hamby, David M. |
| Source Sets | Oregon State University |
| Language | en_US |
| Detected Language | English |
| Type | Thesis/Dissertation |
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