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Browsing Department of Nuclear Engineering and Radiation Health Physics by Author

Browsing Department of Nuclear Engineering and Radiation Health Physics by Author "Reyes, Jose N. Jr"

Now showing items 1-13 of 13

Assessment of level swell measurements in the OSU APEX Test Facility

Ellis, Christopher P. (2000-10-04)

The purposes of this paper are to present the results of an experimental effort to measure the level swell in an air/water system and to generate a methodology for determining the volume-averaged void fraction within the ...
Axial development of two-phase flow parameters in a vertical column

Abel, Kent C. (2002-04-30)

The next generation of nuclear safety analysis computer codes will include detailed modeling of the interfacial area concentration. The interfacial area concentration is the essence of the two-fluid model. It is the mo ...
Characterization of the Advanced Plant Experiment (APEX) passive residual heat removal system heat exchanger

Stevens, Owen L. (1996-06-07)

The Oregon State University (OSU) Radiation Center (RC) is the location of a one quarter scale model of the Westinghouse Electric Corporation advanced light-water nuclear reactor design called the AP-600. The full scal ...
Feasibility study on the medical isotopes production with solution target using OSTR: ⁹⁹Mo and related isotopes

Baik, Seung-Hyuk (1999-03-04)
A general theory of flooding implementing the cuspoid catastrophe

Lafi, Abd Y. (1990-06-06)

The flooding phenomenon can be defined as the maximum attainable flow condition beyond which the well defined countercurrent flow pattern can no longer exist. Thus the countercurrent flow limit (CCFL) or the flooding l ...
Multi application small light water reactor containment analysis and design

Haugh, Brandon Patrick (2002-05-28)

This thesis presents the assessment of the Multi Application Small Light Water Reactor (MASLWR) containment design during steady-state and transient conditions. The MASLWR project is a joint effort between Idaho Nation ...
Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

Colpo, Sarah E. (1999-03-09)

Counter Current Flow Limitation (CCFL) was observed in the pressurizer surge line of the Oregon State University APEX facility during test NRC-10. This test simulated a one-inch diameter cold leg break with a failure o ...
SBLOCA analysis for nuclear plant shutdown operations

Wang, Yi (1994-03-11)

A series of small break loss of coolant accident (SBLOCA) analyses in nuclear plant shutdown operations was simulated using the code RELAP5A,MOD3 version 8.0 to predict the SBLOCA phenomena in the Zion-l nuclear power pl ...
Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

Abel, Kent C. (2005-08-25)

The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for these calculations is known as the two-fluid model. ...
The study of cold leg thermal stratification in APEX-CE

Antoine, Stephanie Y. L. Antoine (2002-04-30)

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 Therma ...
Study of interfacial condensation in a nuclear reactor core makeup tank

Ma, Chang Chun (1993-12-13)

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 ...
A study of return to saturation oscillations in the OSU APEX thermal hydraulic testing facility

Franz, Scott C. (1997-05-06)

The purpose of this paper is to describe the flow oscillations which occur in the AP600 long term cooling test facility at Oregon State University. The AP600 system is an advanced pressurized water reactor design utili ...
A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility

Wachs, Daniel M. (1998-01-06)

The phenomena of interest in this work is the thermal stratification which occurs during the early stages of a loss of coolant accident (LOCA) in the OSU APEX Thermal Hydraulic Test Facility, which is a scaled model of t ...