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Filtering by: Subject Nuclear reactors -- Safety measures -- Cost effectiveness Remove constraint Subject: Nuclear reactors -- Safety measures -- Cost effectiveness Degree Level Doctoral Remove constraint Degree Level: Doctoral

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  • Absorption of methyl iodide by aqueous hydrazine solutions within spray chambers

    Creator:
    Postma, A. K.
    Abstract:
    Absorption of methyl iodide by aqueous hydrazine solutions within spray chambers was studied theoretically and experimentally. The objective of this work was to evaluate the absorption rate of airborne methyl iodide by sprays of hydrazine solutions under conditions expected to exist in post-accident nuclear reactor containment atmospheres. Experimental effort included...
    Resource Type:
    Dissertation
    Full Text:
    consequences in nuclear power plants is very low, safety facilities have been incorporated into reactor

  • Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

    Creator:
    Misner, Alex C.
    Abstract:
    Antineutrino detectors could provide a valuable addition to current safeguards regimes. Antineutrinos are an attractive emission to monitor due to their low interaction cross-section that prevents them from being shielded and the dependence of their spectrum on the power level and isotopic content of a reactor core. While there are...
    Resource Type:
    Dissertation
    Full Text:
    reactor, such observations cannot predict the effect of the diversion of nuclear material on the

  • Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

    Creator:
    Lee, Dongyoung
    Abstract:
    There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive...
    Resource Type:
    Dissertation
    Full Text:
    safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9

  • An investigative approach to study the RETRAN modeling concepts in the analysis of a safety valve discharge transient

    Creator:
    Youssefnia, Mohammad Hossein
    Abstract:
    This study focuses on investigation of the RETRAN modeling concepts in the analysis of a safety valve discharge transient. Three safety valve tests conducted at the Combustion Engineering test facility were chosen for evaluation with RETRAN. It was essential to apply the critical flow boundary condition at the downstream nodes...
    Resource Type:
    Dissertation
    Full Text:
    measure incorporated in the design of reactor safety systems, further pressure relief is also provided

  • Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

    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:
    Figure Page 1.1 SNAP-10 Nuclear Space Reactor 2 1.2 SP-100 Nuclear Space Reactor Configuration