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Thermal conductivity modeling of unrestructured sphere pac nuclear fuels

Creator:: Willison, James Stuart
Abstract:: In order to properly model the temperature distribution of a nuclear fuel pin, the thermal conductivity of the fuel must be known. For sphere pac fuel, the modeling of the conductivity is complicated due to the fact that the fuel is a collection of spheres in a random packed bed....
Resource Type:: Masters Thesis
Full Text:: Uranium Carbide and Mixed Carbide D Material Properties Used to Calculate 76 Gap Conductance E Packing

A two-group study on the gadolinium particle depletion in light water reactor fuel rods

Creator:: Lee, Chungchan
Abstract:: The effect of gadolinia particles on the assembly criticality of a light water reactor was investigated using two 2-group models. The particle effect was calculated by comparing the criticalities of two fuel assemblies, each containing one gadolinia-poisoned rod. For purposes of comparison, both rods contained an equal quantity of gadolinia,...
Resource Type:: Dissertation
Full Text:: criticalities of two fuel assemblies, each containing one gadolinia-poisoned rod. For purposes of comparison

Gadolinium particle depletion in light water reactor fuel rods

Creator:: Hartley, Kenneth D.
Abstract:: Gadolinium is an important element to the Nuclear Fuel Industry. Two of the seven naturally occurring isotopes of gadolinium have very large absorption cross sections for thermal neutrons. The isotopes of ¹⁵⁵ Gd and ¹⁵⁷ Gd readily absorb thermal neutrons and transmute to ¹⁵⁶ Gd and ¹⁵⁸ Gd which are...
Resource Type:: Masters Thesis
Full Text:: Central Core has Burned Away 56 Production and Loss in the Particle Rod when the Central 62 Core is Gone

Control Rod Shadowing Effects in Control Rod Calibrations of The Oregon State TRIGA® Reactor

Creator:: Spoerer, Tracey T.
Abstract:: Control rod calibration experiment results for the Oregon State TRIGA® Reactor (OSTR) immediately following LEU conversion in 2008, and MCNP® 5 predicted rod worths from the 2008 LEU Conversion Safety Analysis Report (CSAR) are discussed. The reactivity worth of the four OSTR control rods are measured using the rod-pull method....
Resource Type:: Masters Thesis
Full Text:: : Control Rod Shadowing Effects in Control Rod Calibrations of The Oregon State TRIGA® Reactor

Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

Creator:: Peguero, Lara M.
Abstract:: Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research reactor currently utilizing IRT-4M fuel made by a single Russian supplier. A candidate for...
Resource Type:: Masters Thesis
Full Text:: the Korean-made High-flux Advanced Neutron Application Reactor (HANARO) fuel rod, which maintains the

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:: compares the amplitude and frequency of vibration between simulated and experimental wire-wrapped rod

An Examination of Critical Heat Flux in a Nuclear Fuel Rod Using an Explicit Finite Difference Scheme

Creator:: Christensen, Alex B.
Abstract:: One of the most important components in the safety analysis of a nuclear reactor is its critical heat flux (CHF), as it can compromise the structural integrity of the clad and lead to the release of fission products into the primary coolant. Groeneveld et. al. has published a series of...
Resource Type:: Honors College Thesis
Full Text:: An Examination of Critical Heat Flux in a Nuclear Fuel Rod

Development of a personal computer-based reactivity meter for a research reactor

Creator:: Bakir, Alla J. M.
Abstract:: A personal computer with a Data Acquisition and Control Adapter interface has been used to monitor the power of the Oregon State University TRIGA Reactor, and from the time behavior of the reactor power the reactivity has been computed using the point kinetics equations and displayed on a digital read-out...
Resource Type:: Masters Thesis
Full Text:: and drop, and control rod calibration. Development of a Personal Computer-based Reactivity Meter

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:: of 100 mm along the entrance region between the two rods at one symmetrical rod power. In addition

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

Creator:: Law, Tyler
Abstract:: A model of the Oregon State TRIGA reactor was developed in Serpent 2 by translating a previously accepted MCNP model. Both models were verified and validated via comparison of each model and data gathered from the core start-up. Reactivity bias in each code was determined. Using the rod drop method,...
Resource Type:: Masters Thesis
Full Text:: repeated until the rod is fully raised. 𝑃 𝑃 0 = 𝑒 𝑡 𝑇 Eq. 12 In this equation, P is power, P0 is

ScholarsArchive@OSU

Thermal conductivity modeling of unrestructured sphere pac nuclear fuels

A two-group study on the gadolinium particle depletion in light water reactor fuel rods

Gadolinium particle depletion in light water reactor fuel rods

Control Rod Shadowing Effects in Control Rod Calibrations of The Oregon State TRIGA® Reactor

Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

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

An Examination of Critical Heat Flux in a Nuclear Fuel Rod Using an Explicit Finite Difference Scheme

Development of a personal computer-based reactivity meter for a research reactor

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

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

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