Index Catalog // ScholarsArchive@OSU

Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel

Creator:: Baker, Ronald Blair
Abstract:: This report presents a refined method for the calculation of fuel centerline temperatures and the linear-heat-rating-to-incipient melting, ' Q'[subscript m], of mixed-oxide fuel typical of that to be used in the Fast Flux Test Facility and in Liquid Metal Fast Breeder Reactors. Of primary concern are the effects of the...
Resource Type:: Masters Thesis
Full Text:: Modeling the thermal effects of fabricated fuel-to

An assessment of describing function methods applied to reactor fuel performance analysis

Creator:: Nielsen, Larry H.
Abstract:: Large digital computer reactor fuel performance codes perform repeated calculations of temperature profiles during transients. The thermal response is required to calculate the mechanical behavior. This mechanical response in turn feeds back to the thermal calculations through mechanisms such as fuel swelling or shrinking, causing changes in the fuel-clad gap...
Resource Type:: Masters Thesis
Full Text:: reactor fuel performance analysis AN ABSTRACT OF THE THESIS OF Larry H. Nielsen for the degree of

The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel

Creator:: Guenther, Richard John
Resource Type:: Masters Thesis
Full Text:: the degree of Master of Science in Nuclear Engineering presented on July 24, 1978 Title: The

Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels

Creator:: Henke, Robert K.
Abstract:: The establishment of any thermal model of reactor fuel requires a thorough understanding of the behavior of the thermal conductivity. This is especially true in the case of sphere pac fuels where the conductivity is a function of many variables beyond those normally affecting conventional fuels. One of these variables,...
Resource Type:: Masters Thesis
Full Text:: Fraction Sphere Pac Nuclear Fuel 42 III.lb Comparison of Experimental and Predicted Values of Thermal

Thermal and mechanical behavior of sphere pac fuel

Creator:: Montgomery, Scott D.
Abstract:: The use of advanced concepts can make the nuclear fuel cycle more efficient by allowing pins to be operated at high powers and to higher burnups. Among the more promising concepts in advanced fuels is sphere pac fuel. In a first attempt to bring together models describing individual phenomena, the...
Resource Type:: Masters Thesis
Full Text:: approved: Redacted for Privacy K1. L. Peiddicord The use of advanced concepts can make the nuclear fuel

A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels

Creator:: Reardon, Patrick Thomas
Resource Type:: Masters Thesis
Full Text:: transfer in ceramic nuclear fuels is complicated by the pres- ence of entrained porosity. In fresh fuel

Direct shear testing of UO₂ sphere-pac nuclear reactor fuel

Creator:: Jenks, Richard P.
Abstract:: The design, development, and utilization of a direct shear test apparatus is presented in this thesis. The effectiveness of the device for determining the friction angle stress state parameter is studied. Two materials, alumina and uranium dioxide, were tested. Alumina microspheres were employed in the initial experiments to simulate the...
Resource Type:: Masters Thesis
Full Text:: Testing_of UO2 Sphere -Pac Nuclear Reactor Fuel Redacted for Privacyapproved: K. L. Peddicord The design

Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR)

Creator:: Bailey, Wendell Jack
Resource Type:: Masters Thesis
Full Text:: boost the amount ·· of' energy produced by the fuel loading. For a nuclear power reactor designed f'or

Fuel-cladding mechanical interaction in simulated sphere pac fuel

Creator:: Vincent, Andrew M.
Abstract:: A study has been made to investigate the fuel-cladding mechanical interaction (FCMI) in sphere pac fuels. An FCMI simulation has been constructed using the JVG Apparatus. This model has been used to investigate the mechanical interaction between a sphere pac bed and a cladding wall in terms of the cladding...
Resource Type:: Masters Thesis
Full Text:: Nuclear Engineering presented on Dec. 9, 1981 Title: Fuel-Cladding Mechanical Interaction In Simulated

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:: properly model the temperature distri- bution of a nuclear fuel pin, the thermal conductivity of the fuel

ScholarsArchive@OSU

Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel

An assessment of describing function methods applied to reactor fuel performance analysis

The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel

Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels

Thermal and mechanical behavior of sphere pac fuel

A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels

Direct shear testing of UO₂ sphere-pac nuclear reactor fuel

Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR)

Fuel-cladding mechanical interaction in simulated sphere pac fuel

Thermal conductivity modeling of unrestructured sphere pac nuclear fuels

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