An analysis of core uncovery in the APEX test facility Public Deposited

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/m900nx577

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  • 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.
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