Index Catalog // ScholarsArchive@OSU

Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility

Creator:: Tang, Hong
Abstract:: Natural convection provides a means for circulating fluids without the use of pumps. This type of system is of great interest for a wide variety of applications, including solar heaters, process industry, and nuclear reactors. Natural convection will play a vital role in the area of passive safety and reliability,...
Resource Type:: Masters Thesis
Full Text:: Engineering Department of Nuclear Engineering Dean of Graduate School I understand that my thesis will

An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets

Creator:: McNair, Gary W.
Abstract:: In fuel pin fabrication, there is no assurance that a fuel pellet will be loaded concentrically. Therefore, azimuthal variations exist in the temperature field giving rise to asymmetry in the neutron flux distribution and pin stresses. Calculations must be made to determine the two dimensional temperature profile which may then...
Resource Type:: Masters Thesis
Full Text:: pepartmene cf Nuclear Engirt ering Redacted for Privacy Dean of Graduate School Date thesis is presented

Fabric composite radiation heat transfer study

Creator:: Gulshan, Zubaida A.
Abstract:: A Fabric Composite Radiation Heat Transfer Study has been conducted to determine the effective emissivities of specific fabric composite materials. The weave of the fabric and the high strength capability of the individual fiber in combination with the thermal conductivity and chemical stability of specific metallic liner, result in a...
Resource Type:: Masters Thesis
Full Text:: Head of Departnfent of Nuclear Engineering Redacted for privacy Dean of cl Date thesis is presented

Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

Creator:: Harter, Jackson R.
Abstract:: The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF) formulation is applied to simulate phonon transport. The neutron transport code Rattlesnake is leveraged in this fashion, slightly modi ed to accept input from variables consistent with phonon transport simulations. Several benchmark problems are modeled to assess the potential...
Resource Type:: Masters Thesis
Full Text:: of the School of Nuclear Science and Engineering Dean of Graduate School I understand that my

Flat Plate Free Convective Heat Transfer

Creator:: Bristol, Benjanmin R.
Abstract:: The OSU MASLWR Test facility is a scaled integral systems LOCA and proof-of-concept test facility for the Multi-Application Small Light Water Reactor design concept. A unique feature of this design is to utilize a small high pressure containment vessel to provide the safety containment function for an integral reactor pressure...
Resource Type:: Masters Thesis
Full Text:: Nuclear Engineering and Radiation Health Physics Dean of the Graduate School I understand that my thesis

A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

Creator:: Byfield, Patrick
Abstract:: The metastable isotope of technetium-99 (Tc-99m) is an important diagnostic tool used in the field of nuclear medicine due to the isotope's 6.0 hour half-life, 140.5 keV γ-decay mechanism, and multiple oxidation states [1,2]. Approximately 70% of the world’s nuclear medicine procedures involve the use of Tc-99m [3]. The conventional...
Resource Type:: Masters Thesis
Full Text:: _____________________________________________________________________ Dean of the Graduate School I understand that my thesis will become part of the

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Creator:: Cox, Jordan
Abstract:: The United States (US) Department of Energy (DOE) has identified the pebble-bed reactor as a high priority for US research with the end goal of licensing a pebble-bed reactor (PBR) for operation in the United States. Before this can be accomplished significant research must be done regarding the safety of...
Resource Type:: Masters Thesis
Full Text:: Science and Engineering Dean of the Graduate School I understand that my thesis will

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Creator:: Goodrich, Sam S.
Abstract:: In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
Resource Type:: Dissertation
Full Text:: Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

Creator:: Blake, Grant C.
Abstract:: The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors...
Resource Type:: Masters Thesis
Full Text:: School of Nuclear Science and Engineering Dean of the Graduate School I understand that my

High pressure condensation heat transfer in the evacuated containment of a small modular reactor

Creator:: Casey, Jason R.
Abstract:: At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support of the NuScale Power Inc. (NSP) design certification progress. The facility will be used to simulate design basis accident performance of the reactor's safety systems....
Resource Type:: Masters Thesis
Full Text:: Dean of the Graduate School I understand that my thesis will become part of the permanent collection

ScholarsArchive@OSU

Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility

An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets

Fabric composite radiation heat transfer study

Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

Flat Plate Free Convective Heat Transfer

A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

High pressure condensation heat transfer in the evacuated containment of a small modular reactor

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