Index Catalog // ScholarsArchive@OSU

Feasibility study on a soluble boron-free small modular reactor

Creator:: Mart, Justin R.
Abstract:: The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
Resource Type:: Masters Thesis
Full Text:: and end of cycle. Investigations of additional strategies involving an advanced control rod

System modeling and reactor design study of an advanced incore thermionic space reactor

Creator:: Lee, Hsing Hui
Abstract:: Incore thermionic space reactor design concepts which operate at a nominal power output range of 20 to 50 kWe are described. Details of the neutronic, thermionic, thermal hydraulics and shielding performance are presented. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that...
Resource Type:: Masters Thesis
Full Text:: Parameters. 28 4. Reference Advanced Thermionic Initiative Driver Rod Parameters. 28 5. Advantages and

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Creator:: VanWinkle, James A.
Abstract:: A study of the oxidation of zircaloy in reactor environments has been undertaken with the goal of characterizing of the Thermal Gradient Test Facility (TGTF) at Teledyne Wah Chang, Albany. A set of oxidation models is presented from the literature, as well as an extensive database of published oxidation test...
Resource Type:: Masters Thesis
Full Text:: examination of the corrosion of a simulated fuel rod under heated conditions. Finally, a manual for the

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:: Abdul-hamid, Shahab A.
Abstract:: Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...
Resource Type:: Masters Thesis
Full Text:: rods to average core power) is thus PNORM = POWERTIsTEp E PWR, The fuel rod normalized power is

Determination of a calculation bias in the MCNP model of the OSTR

Creator:: Kitto, Allyson K.
Abstract:: Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008, the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a Monte Carlo code that can be used for criticality calculations. Until now, a bias in the calculation...
Resource Type:: Masters Thesis
Full Text:: ......................................................................................................24 3.4.1. Control Rod Position

Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systems

Creator:: Gedeon, Stephen R.
Abstract:: Preliminary nuclear design studies have been completed on ten configurations of nuclear reactors for low power (1-30 kWe) space applications utilizing thermionic energy conversion. Additional design studies have been conducted on the TRICE multimegawatt in-core thermionic reactor configuration. In each of the cases, a reactor configuration has been determined which...
Resource Type:: Masters Thesis
Full Text:: thermionic conversion process promises low system specific weight (lb /kW(e)). Thermionic reactor designs

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Creator:: Merritt, Patrick A.
Resource Type:: Masters Thesis
Full Text:: core excess reactivity • The current OSTR model is not accurate enough for rod worth calculations

Development of systems analysis program for space reactor studies

Creator:: Lewis, Bryan R.
Abstract:: An overall systems design code was developed to model an advanced in-core thermionic energy conversion based nuclear reactor system for space applications at power levels of 10 to 50 kWe. The purpose of this work was to provide the overall shell for the systems code and to also provide the...
Resource Type:: Masters Thesis
Full Text:: Figure 14 MCNP Map Window Individual Rod Modification 40 IFEll Edit dgo E radius thickness temp material

Nuclear investigations of the eletrolysis of D₂O using palladium cathodes and platinum anodes

Creator:: Zahm, Lance Leon
Resource Type:: Masters Thesis
Full Text:: electrolyzed gases. A fourth cell utilizes a 4 mm x 45 mm palladium rod. Two constant current power supplies

An investigation of fabric composite heat pipe feasibility issues

Creator:: Marks, Timothy S.
Abstract:: The design of a fabric composite heat pipe has been completed. It is composed of two end caps, between which a fluid containment liner composed of metal foil and an outer structural layer composed of a ceramic fabric is stretched. The interior of the heat pipe is layered with a...
Resource Type:: Masters Thesis
Full Text:: °d- 12 2 ( 1 -erod) 2 SND e rod 4 22 (31) where S is the crimping factor (1.05) and N is the mesh

ScholarsArchive@OSU

Feasibility study on a soluble boron-free small modular reactor

System modeling and reactor design study of an advanced incore thermionic space reactor

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Determination of a calculation bias in the MCNP model of the OSTR

Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systems

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Development of systems analysis program for space reactor studies

Nuclear investigations of the eletrolysis of D₂O using palladium cathodes and platinum anodes

An investigation of fabric composite heat pipe feasibility issues

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