Index Catalog // ScholarsArchive@OSU

Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

Creator:: Deason, Wesley
Abstract:: Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise...
Resource Type:: Masters Thesis
Full Text:: Wesley Deason for the degree of Master of Science in Nuclear Engineering presented on May 31, 2013

System model of a natural circulation integral test facility

Creator:: Galvin, Mark Robert, 1967-
Abstract:: The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since being initiated with a Department of Energy (DoE) grant in 1999. This concept, the Multi-Application Small Light Water Reactor (MASLWR), is an integral pressurized water...
Resource Type:: Dissertation
Full Text:: Formulation . . . . . . . . . . . . . . . . . . . . . . . . . . 31 3.3 Primary Flow Module

Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

Creator:: Wuth, Bradyn J.
Abstract:: Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to model the Korean Atomic Energy Research Institute's SMART reactor, the Žukauskas...
Resource Type:: Masters Thesis
Full Text:: and Cooling Pool Vessels . . . . . . . . . . . . 31 3.2 Data Collection

Multi application small light water reactor containment analysis and design

Creator:: Haugh, Brandon Patrick
Abstract:: 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...
Resource Type:: Masters Thesis
Full Text:: ..................................................................... 31 2.1.6.1 Mass Balance

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:: Castañeda, Juan A.
Abstract:: In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...
Resource Type:: Masters Thesis
Full Text:: 5.1 Scenario 1: PCC Event with SG Heat Removal

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

Creator:: Chadly, Peter Brent
Abstract:: A vital safety concern in the analysis of nuclear power reactors is the thermal hydraulic behavior of the reactor coolant system under steady state and transient conditions. The goal of this study has been to develop an appropriate model for the U-tube type steam generators in a typical pressurized water...
Resource Type:: Masters Thesis
Full Text:: RECIRCULATION RATIO vs. POWER LEVEL 31 11 STEAM GENERATOR SECONDARY MASS INVENTORY vs. POWER LEVEL 32 12

Nonintrusive intelligent monitoring for nuclear power plant emergency classification

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:: 30. Scenario EAL at Time = 868 sec 86 31. Scenario EAL at Time = 1069 sec 87 32. Facts Acquired

SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

Creator:: Hoover, Kyle J.
Abstract:: A scaling analysis of the Oregon State University (OSU) - Multi-Application Small Light Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was improved. The purpose of this study is to support the research of hybrid energy systems, being led by Idaho National Laboratory...
Resource Type:: Masters Thesis
Full Text:: . . . . . . . . . . . . . . . . . . 29 4 Scaling Methodology 31 4.1 Single-Phase Natural Circulation Scaling

A knowledge-based approach for monitoring and situation assessment at nuclear power plants

Creator:: Heaberlin, Joan Oylear
Abstract:: An approach for developing a computer-based aid to assist in monitoring and assessing nuclear power plant status during situations requiring emergency response has been developed. It is based on the representation of regulatory requirements and plant-specific systems and instrumentation in the form of hierarchical rules. Making use of inferencing techniques...
Resource Type:: Dissertation
Full Text:: . KNOWLEDGE BASE STRUCTURE 29 5.2 . FUNCTIONAL REQUIREMENTS 31 5.3 STRATEGY 33 . 5.3.1 Goal Rule

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

Creator:: Hallee, Brian Todd
Abstract:: The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling,...
Resource Type:: Masters Thesis
Full Text:: ] . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 4.2 Detail of CVS/PRHR HX flow connnection to SG-2 lower channel head. [1] 43 4.3 Upper and

ScholarsArchive@OSU

Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

System model of a natural circulation integral test facility

Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

Multi application small light water reactor containment analysis and design

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Thermal hydraulic analysis of a U-tube steam generator in a pressurized water reactor

Nonintrusive intelligent monitoring for nuclear power plant emergency classification

SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

A knowledge-based approach for monitoring and situation assessment at nuclear power plants

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

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