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
| Identifer | oai:union.ndltd.org:ORGSU/oai:ir.library.oregonstate.edu:1957/33969 |
| Date | 13 November 1998 |
| Creators | Rusher, Christopher deCastrique |
| Contributors | Reyes, Jose N. Jr |
| Source Sets | Oregon State University |
| Language | en_US |
| Detected Language | English |
| Type | Thesis/Dissertation |
Page generated in 0.0021 seconds