Index Catalog // ScholarsArchive@OSU

A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

Creator:: Almarshad, Abdullah I. A.
Abstract:: A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
Resource Type:: Dissertation
Full Text:: oxide formed on the waterside surface of 132 reactor-irradiated rods with various fuel burnups. The

Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements

Creator:: Brown, M. Alex
Abstract:: Carboxylic acids have played an important role in the field of actinide (An) and lanthanide (Ln) separations and the reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3-hydroxypentanedioic acid (citric acid) is a promising aqueous complexant that can effectively aid in the separation of transition metals from...
Resource Type:: Dissertation
Full Text:: reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3

Comparison of HEU and LEU neutron spectra in irradiation facilities at the Oregon State TRIGA® reactor

Creator:: Schickler, Robert
Abstract:: In 2008, the Oregon State TRIGA® Reactor (OSTR) was converted from highly-enriched uranium (HEU) fuel lifetime improvement plan (FLIP) fuel to low-enriched uranium (LEU) fuel. This effort was driven and supported by the Department of Energy's (DoE's) Reduced Enrichment for Research and Test Reactors (RERTR) program. The basis behind the...
Resource Type:: Masters Thesis
Full Text:: Reactor-2 (PARR-2). Three types of LEU fuel (UO2 with zircaloy cladding, UO2 with aluminum cladding, and

Design and analysis of a nuclear reactor core for innovative small light water reactors

Creator:: Soldatov, Alexey I.
Abstract:: In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
Resource Type:: Dissertation
Full Text:: fuel assembly design………………… 45 3.2.2. MASLWR reactor vessel geometry……………………………….. 45 3.5.2. CASMO-4

Determination of a calculation bias in the MCNP model of the OSTR

Creator:: Kitto, Allyson K.
Abstract:: Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008, the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a Monte Carlo code that can be used for criticality calculations. Until now, a bias in the calculation...
Resource Type:: Masters Thesis
Full Text:: , the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a

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:: Using HANARO Fuel Rods in WWR-SM Reactor Abstract approved: Todd S. Palmer Interest in increased fuel

Fission Gas Bubble Behavior in Uranium Carbide

Creator:: Matthews, Christopher
Abstract:: The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
Resource Type:: Dissertation
Full Text:: ) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an

Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions

Creator:: Brown, M. Alex
Abstract:: The goal of Advanced Fuel Cycle Initiative program is to efficiently separate and recover actinides in attempts to reprocess irradiated nuclear fuel and reduce the necessary storage volume. In order to facilitate large-scale industrial applications of liquid-liquid separation processes, knowledge of the thermodynamic constants associated with the distribution of metal...
Resource Type:: Masters Thesis
Full Text:: Project Summary ………………………… 2.1 Irradiated Fuel and Reprocessing Chemistry …………. 2.2

Investigation of mixed N,O-donor dipicolinamide derivative ligands for use in nuclear fuel separations

Creator:: Lapka, Joseph
Abstract:: In this work, three isomeric forms of N, N'-diethyl, N, N'-ditolyldipicolinamide (EtTDPA) were synthesized. The elements thorium through americium, which make up a significant portion of the actinides in used nuclear fuel (with the exception of curium), and two fission products, molybdenum and technetium, were tested for their ability to...
Resource Type:: Dissertation
Full Text:: used fuel reprocessing. Degradation products were determined and the effect of their presence on

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Creator:: Brice, Derek J.
Resource Type:: Masters Thesis
Full Text:: criticality calculations In the past, anticipating prompt fuel reprocessing, it used to be that heat

ScholarsArchive@OSU

A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements

Comparison of HEU and LEU neutron spectra in irradiation facilities at the Oregon State TRIGA® reactor

Design and analysis of a nuclear reactor core for innovative small light water reactors

Determination of a calculation bias in the MCNP model of the OSTR

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

Fission Gas Bubble Behavior in Uranium Carbide

Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions

Investigation of mixed N,O-donor dipicolinamide derivative ligands for use in nuclear fuel separations

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

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