Index Catalog // ScholarsArchive@OSU

Heat Loss Characterization of NIST-1's Containment Vessel

Creator:: Yoshiura, Ramon K.
Abstract:: NuScale Power has designed a small modular reactor using natural circulation cooling dependent systems for both steady-state and transient operations. The NuScale Integral Test System (NIST-1) facility was built to supply test data to NuScale Power to verify and validate computer codes for the NuScale Power Mod- ule (NPM) with...
Resource Type:: Masters Thesis
Full Text:: , computational fluid dynamics, condensation, film flow, and heat loss in containments. • Chapter 3 - NIST-1: A

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:: Jackson for the degree of Master of Science in Nuclear Engineering presented on March 17, 2008

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

Creator:: Riley, Thomas H.
Abstract:: The goal of this project was to pave the way for more data-driven decision making when considering safety within Nuclear Engineering by proving the concept of new and innovative accident scenario modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple, if extremely...
Resource Type:: Dissertation
Full Text:: computational power and is very expensive, as the various paths to radionuclide release in an accident

A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

Creator:: Winkle, Tristan
Abstract:: Vibration of nuclear fuel rods is an area of significance for the long-term safe operation of any nuclear power plant. One mechanism of vibration, flow induced vibration (FIV), must be quantified when designing a new core, such as a sodium fast reactor which employs helically-wrapped wire spacers. Experimental work undertaken...
Resource Type:: Masters Thesis
Full Text:: been a shift in the industry towards computational analysis. Given that computation requires no

Finite element transport using Wachspress rational basis functions on quadrilaterals in diffusive regions

Creator:: Davidson, Gregory G.
Abstract:: Wachspress rational functions are ratios of polynomials having certain properties which make them good candidates for basis functions in finite element methods. In addition. it had been theorized that Wachspress rational weight functions should Provide a full-resolution discretization of the neutral particle transport equation in thick diffusive regions, but this...
Resource Type:: Masters Thesis

Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

Creator:: Deason, Wesley
Abstract:: Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise...
Resource Type:: Masters Thesis
Full Text:: Characterization of Fission Product Transport in a Gen

Radiative heat transfer in combustion applications : parallel efficiencies of two gas models, turbulent radiation interactions in particulate laden flows, and coarse mesh finite difference acceleration for improved temporal accuracy

Creator:: Cleveland, Mathew A.
Abstract:: We investigate several aspects of the numerical solution of the radiative transfer equation in the context of coal combustion: the parallel efficiency of two commonly used opacity models, the sensitivity of turbulent radiation interaction (TRI) effects to the presence of coal particulate, and an improvement of the order of temporal...
Resource Type:: Dissertation
Full Text:: increase in computational cost, and the figure of merit for the CMFD-CN scheme is greater than IMC. c

Pressure losses across a 180 degree turn in the AP1000 cooling annulus

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:: pressure loss encountered in other locations in the Passive Containment Cooling System. The Computational

Predicting antineutrino source terms from a high temperature gas reactor

Creator:: Shaughnessy, Andra L.
Abstract:: Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors and are able to determine power levels and burn up throughout a fuel cycle. This technology could allow the IAEA to monitor LWRs remotely and...
Resource Type:: Masters Thesis
Full Text:: observation of these detectors is necessaryl in determining their usefulness, reactor physics simulations

Top-down scaling analysis of the integral reactor vessel test facility

Creator:: Graves, Joshua D.
Abstract:: Oregon State University has conducted research in collaboration with TerraPower, LLC, to perform a top-down scaling analysis of an integrated test facility. The goal of this facility is to simulate transient and quasi-steady phenomena at a reduced scale, including steady-state operation, pump coastdown, natural circulation, reactor head heat transfer, and...
Resource Type:: Masters Thesis
Full Text:: Science in Nuclear Engineering presented on December 7, 2012. Title: Top-Down Scaling Analysis of the

ScholarsArchive@OSU

Heat Loss Characterization of NIST-1's Containment Vessel

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

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

Finite element transport using Wachspress rational basis functions on quadrilaterals in diffusive regions

Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

Radiative heat transfer in combustion applications : parallel efficiencies of two gas models, turbulent radiation interactions in particulate laden flows, and coarse mesh finite difference acceleration for improved temporal accuracy

Pressure losses across a 180 degree turn in the AP1000 cooling annulus

Predicting antineutrino source terms from a high temperature gas reactor

Top-down scaling analysis of the integral reactor vessel test facility

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