Index Catalog // ScholarsArchive@OSU

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:: support codes, the HTTF is a non-nuclear reactor that uses electrical power to analogously represent the

Creator:: Nelson, Roy K.
Abstract:: A one-sixth scaled facility was constructed at Oregon State University to determine the pressure losses around Westinghouse's AP1000 Passive Containment Cooling System. An explanation of the AP1000 Passive Containment Cooling System is given. This study examined the pressure loss and loss coefficient around the 180 degree turn of the Passive...
Resource Type:: Masters Thesis
Full Text:: Nuclear Regulatory Com- mission (NRC) has determined that current reactor licenses are valid for forty

Creator:: Jackson, R. Brian
Abstract:: Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was to study core channel flow reversal susceptibility in the Gas Reactor Test Section (GRTS) at low flow conditions. The second objective was the development of...
Resource Type:: Masters Thesis
Full Text:: Jackson for the degree of Master of Science in Nuclear Engineering presented on March 17, 2008

Creator:: Makinson, Kevin A.
Abstract:: The Run-Ahead Predictive Simulation Software (RAPSS) is an architecture designed for faster-than-real-time decision support for operators of complex networks. To enable further development of the RAPSS methodology, the necessary proof of principle is illustrated in two applications: decision support for shift technical advisors in nuclear power plant control rooms (RAPSS-STA),...
Resource Type:: Dissertation
Full Text:: Anticipated Transients Without Scram BDBA Beyond Design Basis Accident BWR Boiling Water Reactor

Creator:: Goodrich, Sam S.
Abstract:: In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
Resource Type:: Dissertation
Full Text:: OF THE DISSERTATION OF Sam S. Goodrich for the degree of Doctor of Philosophy in Nuclear

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:: Gradecka, Malwina
Abstract:: Since High Temperature Gas-cooled Reactors are being considered as most promising design of upcoming IV Gen reactors, thus key research areas were identified to address safety aspects of this design. Number of simulations and experiments need to be conducted in this field. In this study thermal-hydraulics aspects of coolant flow...
Resource Type:: Dissertation
Full Text:: LP – Lower Plenum MHTGR – Modular High Temperature Gas-cooled Reactor NRC – Nuclear Regulatory

ScholarsArchive@OSU