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  • SBLOCA analysis for nuclear plant shutdown operations

    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:
    analyses of generic safety issues associated with nuclear power plant operation and reports the results to

  • Routine and post-accident analysis of nuclear power plant reactor coolant

    Creator:
    Jolma, Eva I.
    Abstract:
    The 1979 incident at Three Mile Island drew attention to weaknesses in the capability to obtain and analyze reactor coolant samples in an environment where the reactor core incurs significant damage. As a result, the U.S. Nuclear Regulatory Commission promulgated regulations requiring that reactor coolant analytical capabilities be upgraded so...
    Resource Type:
    Masters Thesis
    Full Text:
    Routine and post-accident analysis of nuclear power plant

  • 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:
    Monitoring for Nuclear Power Plant Emergency Classification Abstract approved: Redacted for Privacy Alan H

  • Proof of concept of the use of RAVEN and RELAP5-3D for risk informed safety margin characterization

    Creator:
    Riley, Thomas H.
    Abstract:
    This project was a proof of concept of the use of the RAVEN software, a tool developed for the Risk Informed Safety Margin Characterization (RISMC) approach, with RELAP5-3D. This novel approach combines older probabilistic and mechanistic approaches to look at how and why the complex systems of a nuclear power...
    Resource Type:
    Masters Thesis
    Full Text:
    probabilistic strength of safety margins and discovering and mapping paths to failure in Nuclear Power Plant

  • 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:
    accurately predict the safety margins of the Oregon State Uni- versity Advanced Plant Experiment (APEX