A PC based on-line advanced plant simulator (OLAPS)
for high quality simulations of Portland General
Electric's Trojan Nuclear Facility is presented. OLAPS
is designed to simulate the thermal-hydraulics of the
primary system including core, steam generators, pumps,
piping and pressurizer. The simulations are based on a
five equation model that...
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 National Environmental and Engineering Laboratory (INEEL), NEXANT Bechtel, and Oregon State University. The project is funded under a Nuclear Energy...
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 Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
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 Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility. The results were then...
Condensation Induced Water-Hammer, CIWH, has been an
historical problem for the nuclear power industry over the
past 2 decades. It has caused damage to plant systems, and
considerable anguish to plant operators. This thesis has
embarked on an attempt to characterize the fluid motion, heat
transfer, mixing, and stability of...
Improved methods of determining temperature transients in reactor systems are desired because of recent interest in Pressurized Thermal Shock (PTS) issues. The research presented herein was performed in support of the Nuclear Regulatory Commission's effort to re-evaluate its existing PTS rules. These rules are particularly important to the re-licensing of...
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...
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 plant The first objective is to study the impact of SBLOCA (1" and 2" breaks) on...
In this thesis, I examine Johan Galtung’s theory of violence and discuss how his concepts of cultural and structural violence helps explain the problem of direct violence among Mexican American youth. I argue that cultural violence, mainly dominant narratives of colonialism and masculinity, cause some Mexican American youth to act...
The expansion of a gas within a piston-cylinder arrangement is studied in order to obtain a better understanding of the heat transfer which occurs during this process. While the situation of heat transfer during the expansion of a gas has received considerable attention, the process is still not very well...