Index Catalog // ScholarsArchive@OSU

Creator:: Fundak, Robert
Abstract:: Rapid emergency response decisions from a radiation release are necessary in order to prevent the general public from being exposed to a potential radiation hazard. A one meter exposure rate measurement is all that is necessary to establish relocation and food control areas when the ground is contaminated at the...
Resource Type:: Masters Thesis
Full Text:: necessary to establish relocation and food control areas when the ground is contaminated at the Protective

Creator:: Wang, Yi
Abstract:: 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...
Resource Type:: Masters Thesis
Full Text:: Typical Westinghouse RHRS 4 2. Literature Review 8 2.1 Summary of Principal Safety Concerns 8 2.2

Creator:: Al-Kheliewi, Abdullah S.
Abstract:: A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
Resource Type:: Dissertation
Full Text:: for Privacy performance. It enhances the safety factor in the case of a loss of flow accident

Creator:: Greene, Kenneth R. (Kenneth Ray), 1958-
Abstract:: A prototype real-time process monitoring emergency classification expert system, RT/EM-CLASS, has been developed for use at the Trojan Nuclear Power Plant. This knowledge-based system features the integration of electronically sensed plant data with the menu selection data representation of its predecessor, EM-CLASS. This prototype demonstrates the techniques required to acquire...
Resource Type:: Dissertation
Full Text:: factors engineering (Safety Parameter Display System, SPDS, to convey clearly the state of the plant). It

Creator:: Rusher, Christopher deCastrique
Abstract:: 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...
Resource Type:: Masters Thesis
Full Text:: examine AP600 passive safety system performance, particularly during long term cooling. The NRC-25

Creator:: Wachs, Daniel M.
Abstract:: The phenomena of interest in this work is the thermal stratification which occurs during the early stages of a loss of coolant accident (LOCA) in the OSU APEX Thermal Hydraulic Test Facility, which is a scaled model of the Westinghouse AP600 nuclear power plant. Thermal stratification has been linked to...
Resource Type:: Masters Thesis
Full Text:: genuine decency and dedication are the standard by which I will always measure myself. ii TABLE OF

ScholarsArchive@OSU