Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003. / Thesis supervisor: Neil E. Todreas. Includes bibliographical references (p. 117-121). Also available online.

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Thesis (M.S.)--Oregon State University, 2008. / Printout. Includes bibliographical references (leaves 84-85). Also available on the World Wide Web.

Thesis (M. Phil.)--University of Hong Kong, 1990.

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 of three of four of the fourth-stage Automatic Depressurization System (ADS) valves. The result was a high vapor flow rate through ADS 1-3, that caused CCFL in the pressurizer surge line and liquid holdup in the pressurizer. Because this liquid was not available for core cooling, further study of the passive safety systems in the AP600 under Mode 5 Cold Shutdown conditions was deemed necessary. An analysis of the AP600 geometry and the existing CCFL database determined that Kutateladze scaling is appropriate for the APEX and AP600 surge lines. The Kutateladze CCFL correlation was used to assess CCFL in the APEX and AP600 pressurizer surge lines under Mode 5 Cold Shutdown conditions. The results indicate that CCFL would be expected in the pressurizer surge lines at low pressures and decay powers prior to ADS 4 actuation. Test NRC-35 examined CCFL and provided data to benchmark NRC's thermal hydraulic analysis codes. This thesis presents the results of test NRC-35 and the supporting CCFL calculations. / Graduation date: 1999

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 the Westinghouse AP600 nuclear power plant. Thermal stratification has been linked to the occurrence of pressurized thermal shock (PTS). Analysis of the OSU APEX facility data has allowed the determination of an onset criteria and support for the postulated mechanisms leading to thermal stratification. CFX 4.1, a computational fluid dynamics code, was used to generate a model of the cold legs and the downcomer and the phenomena occurring within them. The following are the accomplishments of the work contained within this report; Determined the causes of thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. Predicted the onset of thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. Modeled the phenomena associated with thermal stratification in the cold legs of the Westinghouse Advanced Passive 600 MW (AP600) nuclear power plant. / Graduation date: 1998

The Department of Nuclear Engineering at Oregon State University has performed a series of confirmatory tests for the United States Nuclear Regulatory Commission (USNRC). These tests have been conducted in the Advanced Plant Experiment (APEX) Facility which is a one quarter height scaled simulation of the Westinghouse Advanced Passive 600 megawatt electric (AP600) pressurized water reactor. The purpose of the testing program is to examine AP600 passive safety system performance, particularly during long term cooling. The NRC-25 series tests represents a parametric study to determine the minimum liquid reserves required to prevent a temperature excursion in the APEX core. The tests were initiated with a failure of all passive safety systems with the exception of portions of the fourth stage of the Automatic Depressurization System (ADS-4) and the In-containment Refueling Water Storage Tank (IRWST) injection system. These tests were concluded upon the onset of IRWST injection or core uncovery as determined by a temperature excursion in the core. The purpose of this thesis is to present the results of the NRC-25 test series. This includes a theoretical model which was developed to predict core liquid inventory during an ADS-4 blowdown. The NRC-25 test series was used to benchmark a theoretical model derived using the mass and energy conservation equations, the perfect gas law, and a critical gas flow model. It will be shown that this model agrees with the experimental data quite well. / Graduation date: 1999

Thesis (Ph. D.)--University of Missouri-Columbia, 2002. / Typescript. Vita. Includes bibliographical references (leaves 122-128). Also available on the Internet.

Thesis (Ph. D.)--University of Missouri-Columbia, 2002. / Typescript. Vita. Includes bibliographical references (leaves 122-128). Also available on the Internet.