Index Catalog // ScholarsArchive@OSU

Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

Creator:: Marcum, Wade R.
Abstract:: Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: _____________________________________________________________________ Brian G

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

Creator:: Robinson, Adam B.
Abstract:: This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such...
Resource Type:: Masters Thesis

Development of a heat transfer coefficient for a single mist nozzle impinging on a heated thin sheet of Alloy 304 Stainless Steel using infrared thermography

Creator:: Cadell, Seth R.
Abstract:: A purpose built facility was designed, built and operated at the Advanced Thermal Hydraulic Research Laboratory, which is located at Oregon State University. This facility was used to heat a plate of Alloy 304 Stainless Steel to 800 °C and then cool the plate using a fine mist of water...
Resource Type:: Masters Thesis
Full Text:: approved: Brian G. Woods Qiao Wu A purpose built

System model of a natural circulation integral test facility

Creator:: Galvin, Mark Robert, 1967-
Abstract:: The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since being initiated with a Department of Energy (DoE) grant in 1999. This concept, the Multi-Application Small Light Water Reactor (MASLWR), is an integral pressurized water...
Resource Type:: Dissertation
Full Text:: Facility Abstract approved: Brian G. Woods The Department of Nuclear Engineering and Radiation Health

Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

Creator:: Nelson, Benjamin L.
Abstract:: The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility be built for the validation of computer codes for the safe operation of the VHTR. The scaling of the prismatic core configuration has been analyzed...
Resource Type:: Masters Thesis
Full Text:: : _____________________________________________________________________ Brian G. Woods The Very High Temperature Reactor (VHTR) has two possible core

A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

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:: fly_leaf AN ABSTRACT OF THESIS OF R. Brian

Extending the applicability of implicit Monte Carlo Diffusion : frequency dependence and variance reduction using the difference formulation

Creator:: Cleveland, Mathew A.
Abstract:: The intent of this work is to extend Implicit Monte Carlo Diffusion (IMD)[Gen. 2001] to account for frequency dependence and to incorporate the difference formulation[Szo. 2005] as a source manipulation variance reduction technique. This work shows the derivation of the probabilities and the associated proofs which govern the frequency dependent...
Resource Type:: Masters Thesis
Full Text:: ; Dr. Brian Woods, Dr. Sourabh Apte, and Dr. Ken Krane, for their time and commitment to my thesis

Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

Creator:: Abel, Kent C.
Abstract:: The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for these calculations is known as the two-fluid model. It is the most accurate of the two-phase models since it considers each phase independently and links...
Resource Type:: Dissertation
Full Text:: V. Pence, Dr. Brian Woods and Dr. Vinod Narayanan, for their valuable comments and their time. I

Effects of fluid axial conduction on liquid metal natural circulation and linear stability

Creator:: Sabharwall, Piyush
Abstract:: The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through non-dimensional analysis, steady-state assessment, and linear perturbation evaluation. The Nyquist criterion and a root search method were employed to find the linear stability boundary of both forward and backward circulations....
Resource Type:: Masters Thesis
Full Text:: also like to thank the other members of my committee, Dr. Brian Woods, Dr. Richard Peterson and Dr

Phase distribution parameter determination by neutron radiography

Creator:: Skinner, Jesse B.
Abstract:: A phase distribution parameter has been added to the one-dimensional two-phase horizontal flow conservation equations. The phase distribution parameter was incorporated into the conservation equations in an attempt to add stability and remove correlation switching by incorporating gravity. Determination of the phase distribution parameter requires an average void fraction profile...
Resource Type:: Masters Thesis
Full Text:: : g g Q j A = (1.1) f f Q j A = (1.2) In the above equations j is

ScholarsArchive@OSU

Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

Development of a heat transfer coefficient for a single mist nozzle impinging on a heated thin sheet of Alloy 304 Stainless Steel using infrared thermography

System model of a natural circulation integral test facility

Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

Extending the applicability of implicit Monte Carlo Diffusion : frequency dependence and variance reduction using the difference formulation

Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

Effects of fluid axial conduction on liquid metal natural circulation and linear stability

Phase distribution parameter determination by neutron radiography

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