Index Catalog // ScholarsArchive@OSU

Optimization of in-core nuclear fuel management in a pressurized water reactor

Creator:: Stout, Richard Bartholomew
Abstract:: Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and to minimize the possibility of fuel failure. A computer code called SHUFLE was developed for pressurized water reactors which shuffles the fuel in search of...
Resource Type:: Dissertation
Full Text:: : OPTIMIZATION OF IN-CORE NUCLEAR FUEL MANAGE- MENT IN A PRESSURIZED WATER REACTOR Redacted for privacy

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

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

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

ScholarsArchive@OSU

Optimization of in-core nuclear fuel management in a pressurized water reactor

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

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

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

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