Index Catalog // ScholarsArchive@OSU

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

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Creator:: Weiss, Aaron W.
Abstract:: A large, multi-year experimental program has been conducted to develop a strain gaging program for application to the flow testing of prototypic, plate-type fuel for high performance research reactors. This test program has resulted in the selection of appropriate strain gage construction, adhesives, and protective coatings to allow the acquisition...
Resource Type:: Masters Thesis
Full Text:: converted to LEU fuel as of February, 2011 according to the National Nuclear Security Administration (2011

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

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

Creator:: Jensen, Philip
Abstract:: The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypical plate type fuel. OSU's fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI's...
Resource Type:: Masters Thesis
Full Text:: enriched uranium (HEU) to a low enriched uranium (LEU) fuel in an effort to reduce nuclear proliferation

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

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

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Fuel-cladding mechanical interaction in simulated sphere pac fuel

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

Thermal conductivity modeling of unrestructured sphere pac nuclear fuels

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