Index Catalog // ScholarsArchive@OSU

Creator:: Goodrich, Sam S.
Abstract:: Currently there is a great amount of interest in the phenomena of natural circulation as a cooling mechanism for normal operation as well as emergency conditions in nuclear reactors and spent fuel pools. In order to better understand this phenomena for the specific geometry of vertical, heated rods in water,...
Resource Type:: Masters Thesis
Full Text:: facility was designed and constructed at Oregon State University. This facility, named the Laser-Imaged

Creator:: Aldridge, Robert J.
Abstract:: In 2008, the Department of Energy (DOE) and Nuclear Regulatory Commission (NCR) decided that the Next Generation Nuclear Plant (NGNP) would be the Very High Temperature Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University was tasked with designing, building, and operating a...
Resource Type:: Masters Thesis
Full Text:: Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University

Creator:: Utberg, John E., Jr
Abstract:: The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...
Resource Type:: Masters Thesis
Full Text:: . The High Temperature Test Facility (HTTF) at Oregon State University (OSU) is a scaled integral test

Creator:: Ropon, Kimberly
Abstract:: The Department of Nuclear Engineering at Oregon State University has recently introduced a neutron radiography facility (OSNRF). The facility is dependent on a neutron source established by the OSU TRIGA® Reactor (OSTR). It was unknown how accurately a computerized model of the OSTR in conjunction with the OSNRF could represent...
Resource Type:: Masters Thesis
Full Text:: . Title: Mapping Dose Rate of the Oregon State University Neutron Radiography Facility J Abstract

Creator:: Castañeda, Juan A.
Abstract:: In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...
Resource Type:: Masters Thesis
Full Text:: licensing and validation of the VHTR, Oregon State University was tasked to develop a high temperature

Creator:: Schickler, Robert
Abstract:: In 2008, the Oregon State TRIGA® Reactor (OSTR) was converted from highly-enriched uranium (HEU) fuel lifetime improvement plan (FLIP) fuel to low-enriched uranium (LEU) fuel. This effort was driven and supported by the Department of Energy's (DoE's) Reduced Enrichment for Research and Test Reactors (RERTR) program. The basis behind the...
Resource Type:: Masters Thesis
Full Text:: Facilities at the Oregon State TRIGA Reactor AN ABSTRACT OF THE THESIS OF Robert Schickler for

Creator:: Byfield, Patrick
Abstract:: The metastable isotope of technetium-99 (Tc-99m) is an important diagnostic tool used in the field of nuclear medicine due to the isotope's 6.0 hour half-life, 140.5 keV γ-decay mechanism, and multiple oxidation states [1,2]. Approximately 70% of the world’s nuclear medicine procedures involve the use of Tc-99m [3]. The conventional...
Resource Type:: Masters Thesis
Full Text:: world susceptible to Tc-99m shortages in the event of multiple reactor shutdowns [5]. Oregon

Creator:: Hummel, Andrew J.
Abstract:: The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be...
Resource Type:: Dissertation
Full Text:: : Molybdenum-99 Production in the Oregon State TRIGA Reactor: Analysis of the Reactor Design using a new LEU

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