Search Constraints

Start Over
Filtering by: Alternative title ssim SG 2 Remove constraint Alternative title ssim: SG 2 Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering Peer Reviewed No Remove constraint Peer Reviewed: No

Search Results

  • Experimental investigation of condensation phenomena inside a U-tube steam generator

    Creator:
    Collins, Brian A.
    Abstract:
    Reflux condensation tests examining steam condensation in a PWR steam generator (SG) were conducted at the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility from 2005 through 2007. The experimental data collected will provide a basis to assess TRACE steam generator modeling techniques and assist in development of...
    Resource Type:
    Masters Thesis

  • 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:
    Reactor . . . . . . . . . . . . . . . . 2 1.2 Anticipatory Control of Natural Circulation Reactor Plants

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.1.1 NuScale Power, Inc. . . . . . . . . . . . . . . . . . . . . . . . 5 1.1.2 Multi

  • 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:
    ......................................................................................... 1 2 LITERATURE iuvmw

  • 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:
    ................................................................................................... 75 5.2 Scenario 2: PCC Event with SG and Cross-Duct Vessel Break

  • 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:
    . INTRODUCTION AND OBJECTIVES 1 II. BACKGROUND INFORMATION 3 1. Steam Generator Description 3 2. RETRAN

  • 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:
    action level classes: (1) notification of unusual event, (2) alert, (3) site area emergency, and (4

  • RELAP5-3D modeling of ADS blowdown of MASLWR facility

    Creator:
    Bowser, Christopher Jordan
    Abstract:
    Oregon State University has hosted an International Atomic Energy Agency (IAEA) International Collaborative Standard Problem (ICSP) through testing conducted on the Multi-Application Small Light Water (MASLWR) facility. The MASLWR facility features a full-time natural circulation loop in the primary vessel and a unique pressure suppression device for accident scenarios. Automatic...
    Resource Type:
    Masters Thesis
    Full Text:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2. LITERATURE REVIEW

  • 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:
    in progress. Table of Contents 1. Introduction 1 2. Background 3 2.1. Expert Systems 4 2.2

  • 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:
    Reactors . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Objectives