Index Catalog // ScholarsArchive@OSU

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

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

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

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

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

Reactor physics model of the Advanced Test Reactor using TRIGA® fuel through application of Serpent 2

Creator:: Lyons, Jennifer
Abstract:: The Advanced Test Reactor (ATR), under the Reduced Enrichment for Research and Test Reactors (RERTR) Program and the Global Threat Reduction Initiative (GTRI), is conducting feasibility studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low enriched uranium (LEU) composition. These studies have...
Resource Type:: Masters Thesis
Full Text:: on July 31, 2013. Title: Reactor Physics Model of the Advanced Test Reactor using TRIGA® Fuel

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

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

Creator:: Alberti, Anthony L.
Abstract:: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
Resource Type:: Masters Thesis
Full Text:: S. Palmer With the advent of next generation reactor systems and new fuel designs, the U.S. Depart

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

ScholarsArchive@OSU

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

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

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

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

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

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

Reactor physics model of the Advanced Test Reactor using TRIGA® fuel through application of Serpent 2

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

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

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

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