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Plutonium Recycling via Iterative Mixed-Oxide Fuel Reprocessing

Creator:: Perlin, Michael A.
Abstract:: Poster presented at Idaho National Laboratory for the 2014 Fuel Cycle Technologies Annual Review Meeting.
Resource Type:: Poster
Full Text:: Plutonium Recycling via Iterative Mixed-Oxide Fuel Reprocessing

The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing

Creator:: Matteson, Brent Searle
Abstract:: Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fission products as a result of the uranium fission process and neutron activation that occur in commercial light water power reactors. Recent environmental and nuclear proliferation concerns have spawned the development of advanced reprocessing techniques to close the nuclear fuel...
Resource Type:: Dissertation
Full Text:: advanced reprocessing techniques to close the nuclear fuel cycle. By separating specific elemental groups

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

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

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

Creator:: Gullekson, Brian J.
Abstract:: Partitioning of trivalent actinides (in particular, americium and curium) from the fission produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste disposal. Several solvent extraction processes have been developed to address these chemically difficult separations. The historically employed TALSPEAK Process utilizes di-2-ethylhexyl...
Resource Type:: Dissertation
Full Text:: produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste

SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

Creator:: Hoover, Kyle J.
Abstract:: A scaling analysis of the Oregon State University (OSU) - Multi-Application Small Light Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was improved. The purpose of this study is to support the research of hybrid energy systems, being led by Idaho National Laboratory...
Resource Type:: Masters Thesis
Full Text:: Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was

Numerical solutions of the neutron transport equation

Creator:: Skeen, David Roy
Abstract:: Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted accurately. This leads to the high cost computer computations and a search for cheaper yet still accurate methods. For this paper we have chosen to study an alternate method for calculating thermal neutron cell...
Resource Type:: Dissertation
Full Text:: studies are expensive. For an example, let us examine a fuel management program. A typical reactor fuel

Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases

Creator:: Gullekson, Brian J.
Abstract:: Spent nuclear fuel (SNF) resultant from the generation of nuclear power is a chemically and radiologically diverse system which is advantageous to chemically process prior to geologic disposal. Hydrometallurgy is the primary technology for chemical processing for light water reactor spent fuels, where spent fuel is dissolved in an acid...
Resource Type:: Masters Thesis
Full Text:: water reactor spent fuels, where spent fuel is dissolved in an acid for liquid based separations. The

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:: Abdul-hamid, Shahab A.
Abstract:: Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...
Resource Type:: Masters Thesis
Full Text:: is uniformly mixed in the fuel. MCNPBURN was benchmarked using a standard Pressurized Water Reactor

ScholarsArchive@OSU

Plutonium Recycling via Iterative Mixed-Oxide Fuel Reprocessing

The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing

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

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

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

Numerical solutions of the neutron transport equation

Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

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