A one-sixth scaled facility was constructed at Oregon State University to determine
the pressure losses around Westinghouse's AP1000 Passive Containment
Cooling System. An explanation of the AP1000 Passive Containment Cooling System
is given. This study examined the pressure loss and loss coefficient around the
180 degree turn of the Passive...
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...
Steam interfacial condensation in a core makeup tank was simulated using the
code RELAP5/MOD3 version 8.0 to predict the violent pressure oscillation phenomena
in a core makeup tank. Six base cases were carried out to study the effects of back
pressure and of vacuum conditions produced in the core makeup...
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...
The purpose of this paper is to describe the flow oscillations which occur in the
AP600 long term cooling test facility at Oregon State University. The AP600 system is
an advanced pressurized water reactor design utilizing passive emergency cooling
systems.
A few hours after the initiation of a cold leg...
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...
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...
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...
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...
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...