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Kinetics of the decomposition of organic reactor coolants

Creator:: De Halas, Don Richard
Resource Type:: Dissertation
Full Text:: properties enable the con- struction of a nuclear reactor without the high pressure piping and expensive

Research reactor coolant monitoring using automated gamma ray spectrometry

Creator:: TenBrook, Warren Kermit
Abstract:: An integrated sampling and gamma ray spectrometry system has been developed for analysis of TRIGA reactor primary cooling water. A microcomputer controls pumps and valves using BASIC and assembly language programs to pump 300 ml liquid samples into a reference geometry surrounding a Ge(Li) detector. Gamma ray spectra are acquired...
Resource Type:: Masters Thesis
Full Text:: Oregon State University TRIGA Reactor (OSTR) 24 4. Schematic diagram of the OSTR water cooling and

High Pressure Condensation in an SMR Containment

Creator:: Mullin, Etienne M.
Abstract:: The Oregon State University Multi-Application Small Light Water Reactor test facility is employed in a series tests to evaluate condensation heat transfer in small, high pressure containment vessels characteristic of small modular reactor designs under development. This integral system test facility was constructed to demonstrate the feasibility of a pioneering...
Resource Type:: Masters Thesis
Full Text:: Plate CPV Cooling Pool Vessel RPV Reactor Pressure Vessel ADS Automatic Depressurization System P&ID

A study of buoyant backflow in vertical injection lines

Creator:: King, John Barry
Abstract:: In the event of a small break loss of coolant accident (SBLOCA) in a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to compensate for the coolant loss. When this flow rate is less than a critical value, however, the hot fluid in the cold...
Resource Type:: Dissertation
Full Text:: a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to

Scaling of the thermal mixing processes within the lower plenums of VHTR designs

Creator:: Van Horn, Matthew A.
Abstract:: The Very High Temperature Reactor (VHTR) design was one of six designs chosen for development under the Generation IV initiative. Thermal mixing of the coolant at the exit of the reactor has been a common concern for VHTR reactor designs. Thermal mixing processes are commonly investigated through the use of...
Resource Type:: Masters Thesis

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

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:: engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent

Design, fabrication, and characterization of the laser-imaged natural circulation (LINC) facility

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

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

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

Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

Creator:: Danielson, Jordan J.
Abstract:: All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing instruments are differential pressure sensing meters, which are invasive and could be the failure source in the pressure boundary of the primary coolant system. In...
Resource Type:: Masters Thesis
Full Text:: development of SMRs. A nuclear reactor is considered to be "small" if the design output is 300 MWe or less [11

Quantified PIRT and uncertainty quantification for computer code validation

Creator:: Luo, Hu
Abstract:: This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
Resource Type:: Dissertation
Full Text:: procedures to rule reactor Emergency Core Cooling System (ECCS) analysis in 10CFR50.46 and Appendix K in

ScholarsArchive@OSU

Kinetics of the decomposition of organic reactor coolants

Research reactor coolant monitoring using automated gamma ray spectrometry

High Pressure Condensation in an SMR Containment

A study of buoyant backflow in vertical injection lines

Scaling of the thermal mixing processes within the lower plenums of VHTR designs

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Design, fabrication, and characterization of the laser-imaged natural circulation (LINC) facility

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

Quantified PIRT and uncertainty quantification for computer code validation

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