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:: (IAEA) classifies any commercial nuclear power reactor with a design power output of 300 MW electric

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:: ] ............................................. 7 Figure 1-5: The MHTGR Reactor Cavity Cooling System [6

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:: Temperature Gas-Cooled Reactor NGNP Next Generation Nuclear Plant OSU Oregon State University PCC

Creator:: Chinudomsub, Kittisak
Abstract:: The Safety Analysis Report (SAR) of the Oregon State University TRIGA Research Reactor (OSTR) was prepared and used as a safety baseline for the reactor's operation since 1968. Although, in general, revision of the Safety Analysis Report of a research reactor is not a regulation requirement, it should be revised...
Resource Type:: Masters Thesis
Full Text:: Waste Management Programs as Described in the Oregon State University TRIGA Research Reactor Safety

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:: Love, Ian J.
Abstract:: High purity niobium metal is used in the construction of superconducting radio frequency (SRF) cavities in superconducting particle accelerators, such as the Large Hadron Collider (LHC) at CERN or the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory. The usual method for characterizing the impurities in this niobium, the...
Resource Type:: Masters Thesis
Full Text:: of the PGNAA facility at the Oregon State University TRIGA ® Reactor (OSTR). Two “standard

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

ScholarsArchive@OSU