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 scale AP-600 is a 600 megawatt electric
nuclear power plant that incorporates unique passive systems to perform the safety
functions currently required of all existing nuclear power plants. Passive safety refers to
a system's ability to perform its desired function using natural forces such as gravity and
natural circulation. This reduces the reliance on active systems to assure plant safety.
The Advanced Plant Experiment (APEX) at the OSU RC is an electrically heated
simulation of the AP-600 that includes the Nuclear Steam Supply System (NSSS) and all
of the passive safety systems. The APEX facility was funded by the United States
Department of Energy and the Westinghouse Electric Corporation. The facility was built
to perform the long term cooling tests necessary for design certification of the AP-600.
The data taken will be used to benchmark the thermal hydraulic computer codes applied
in the design certification process and to better understand the phenomena involved in the
full scale AP-600.
This paper presents the analysis of the Passive Residual Heat Removal System
(PRHR) and in particular the PRHR's "c"-shaped heat exchanger (PRHR Hx). This paper
includes analysis and modeling of the PRHR Hx including: hydraulic flow parameters, heat rejection capability, an empirical correlation for determining pressure drop, and an examination of the flow phenomena that occurs in the tank in which the heat exchanger is installed. / Graduation date: 1997
| Identifer | oai:union.ndltd.org:ORGSU/oai:ir.library.oregonstate.edu:1957/34482 |
| Date | 07 June 1996 |
| Creators | Stevens, Owen L. |
| Contributors | Reyes, Jose N. Jr, Davis, Lorin R. |
| Source Sets | Oregon State University |
| Language | en_US |
| Detected Language | English |
| Type | Thesis/Dissertation |
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