Index Catalog // ScholarsArchive@OSU

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Creator:: VanWinkle, James A.
Abstract:: A study of the oxidation of zircaloy in reactor environments has been undertaken with the goal of characterizing of the Thermal Gradient Test Facility (TGTF) at Teledyne Wah Chang, Albany. A set of oxidation models is presented from the literature, as well as an extensive database of published oxidation test...
Resource Type:: Masters Thesis
Full Text:: Oxidation of Zircaloy-4 in pressurized water reactor

Thermal hydraulic analysis of a pressurized water reactor

Creator:: Oylear, Joan Marie
Resource Type:: Masters Thesis
Full Text:: Thermal Hydraulic Analysis of a Pressurized Water Reactor

An evaluation of a neutron "flux trap" control scheme for pressurized water reactors

Creator:: Anderson, Michael Jay
Abstract:: Pressurized water reactors are presently controlled by the use of materials which absorb neutrons as their only effect; this reduces the neutron economy of the system, since these neutrons are lost without helping to maintain the chain reaction. The system examined in this study replaces these absorbing materials with a...
Resource Type:: Masters Thesis
Full Text:: pressurized water reactors AN ABSTRACT OF THE THESIS OF Michael J. Anderson for the degree of Master of

Development and implementation of an improved formulation of the momentum balance for a Once Through Steam Generator transient model

Creator:: Luo, Shyr Tung
Abstract:: A detailed formulation of the momentum equation including the Baroczy model for two phase friction is presented in this thesis. Numerical techniques for solving this equation along with the remainder of the describing equations are also presented. This model has been incorporated into an existing thermal hydraulic code for simulating...
Resource Type:: Masters Thesis
Full Text:: itself, the steam generator is one of the principal components in a pressurized water reactor (PWR

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

Creator:: Chadly, Peter Brent
Abstract:: A vital safety concern in the analysis of nuclear power reactors is the thermal hydraulic behavior of the reactor coolant system under steady state and transient conditions. The goal of this study has been to develop an appropriate model for the U-tube type steam generators in a typical pressurized water...
Resource Type:: Masters Thesis
Full Text:: a pressurized water reactor AN ABSTRACT OF THE THESIS OF Peter B. Chadly for the degree of Master

The study of cold leg thermal stratification in APEX-CE

Creator:: Antoine, Stephanie Y. L. Antoine
Abstract:: This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
Resource Type:: Masters Thesis
Full Text:: Loop Water in Pressurized Water Reactor Cold Legs" [10], Sun et al. studied the phenomenon of

Experimental investigation of condensation phenomena inside a U-tube steam generator

Creator:: Collins, Brian A.
Abstract:: Reflux condensation tests examining steam condensation in a PWR steam generator (SG) were conducted at the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility from 2005 through 2007. The experimental data collected will provide a basis to assess TRACE steam generator modeling techniques and assist in development of...
Resource Type:: Masters Thesis

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Creator:: Mai, Anh T.
Abstract:: The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
Resource Type:: Masters Thesis
Full Text:: -Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water

Blowdown transient critical heat flux

Creator:: Moussaoui, Musa A.
Abstract:: Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large...
Resource Type:: Masters Thesis
Full Text:: prototypic pressurized water reactor (PWR) conditions. Further, LOCA induced transient CHF is not well

Study of interfacial condensation in a nuclear reactor core makeup tank

Creator:: Ma, Chang Chun
Abstract:: Steam interfacial condensation in a core makeup tank was simulated using the code RELAP5/MOD3 version 8.0 to predict the violent pressure oscillation phenomena in a core makeup tank. Six base cases were carried out to study the effects of back pressure and of vacuum conditions produced in the core makeup...
Resource Type:: Masters Thesis
Full Text:: improvements in these areas. The AP600 is a two-loop pressurized water reactor. Each loop comprises one hot

ScholarsArchive@OSU

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Thermal hydraulic analysis of a pressurized water reactor

An evaluation of a neutron "flux trap" control scheme for pressurized water reactors

Development and implementation of an improved formulation of the momentum balance for a Once Through Steam Generator transient model

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

The study of cold leg thermal stratification in APEX-CE

Experimental investigation of condensation phenomena inside a U-tube steam generator

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Blowdown transient critical heat flux

Study of interfacial condensation in a nuclear reactor core makeup tank

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

Date

Decade

Degree Field

Degree Level

Degree Name

File Format

Language

License

Non-Academic Affiliation

Peer Reviewed

Resource Type

Rights Statement

Subject

Search Constraints

Search Results

Limit your search