Open Access. Powered by Scholars. Published by Universities.®
Physical Sciences and Mathematics
University of Nevada, Las Vegas
UNLV Theses, Dissertations, Professional Papers, and Capstones
- Keyword
-
- Activation foil; Beryllium compounds; MCNPX; Monte Carlo method; Neutron activation analysis; Neutron flux; Nuclear activation analysis; Plutonium-beryllium (Pu-Be); Plutonium compounds (1)
- Colon (Anatomy) — Cancer; Colorectal Cancer; Cox Proportional Hazard; CRC; Minorities; Proportional hazards models; Racial and Ethnic Disparities; Survival Analysis (1)
Articles 1 - 2 of 2
Full-Text Articles in Medicine and Health Sciences
The Determinants Of Colorectal Cancer Survival Disparities In Nevada, Lucas N. Wassira
The Determinants Of Colorectal Cancer Survival Disparities In Nevada, Lucas N. Wassira
UNLV Theses, Dissertations, Professional Papers, and Capstones
Different population groups across Nevada and throughout the United States suffer disproportionately from colorectal cancer and its after-effects. Overcoming cancer health disparities is important for lessening the burden of cancer. There has been an overall decline in the incidence of and mortality from colorectal cancer (CRC). This is likely due, in part, to the increasing use of screening procedures such as Fecal Occult Blood Test (FOBT) and/or endoscopy, which can reduce the risk of CRC mortality by fifty percent. Nevertheless, screening procedures are routinely used by only fifty percent of Americans aged fifty years and older. Despite overall mortality decreasing …
Neutron Flux And Energy Characterization Of A Plutonium-Beryllium Isotopic Neutron Source By Monte Carlo Simulation With Verification By Neutron Activation Analysis, Zachary R. Harvey
Neutron Flux And Energy Characterization Of A Plutonium-Beryllium Isotopic Neutron Source By Monte Carlo Simulation With Verification By Neutron Activation Analysis, Zachary R. Harvey
UNLV Theses, Dissertations, Professional Papers, and Capstones
The purpose of this research was to characterize the neutron energy distribution and flux emitted from the UNLV plutonium-beryllium source, serial number MRC-N-W PuBe 453. This was accomplished through the use of the MCNPX/5 Monte-Carlo particle transport code to simulate radiation interactions within the physical environment of the source and its surroundings. The moderating drum currently containing the source as well as all of the sampling ports were accurately modeled in MCNPX/5. This geometry was then used to simulate the neutron interactions taking place in these geometries. The results of the simulations were then verified by the use of specifically …