Search Constraints

Start Over
Filtering by: Alternative title ssim Internal report no. 125 Remove constraint Alternative title ssim: Internal report no. 125 Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian

Search Results

  • Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

    Creator:
    Higgins, Anton
    Abstract:
    The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
    Resource Type:
    Masters Thesis
    Full Text:
    States currently has no infrastructure to provide a fast neutron flux for research purposes. With the

  • Quantification of dry concentration factor for Cs-134 in marine diatom Thalassiosira Weissflogii

    Creator:
    Krzyaniak, Nathan Anthony
    Abstract:
    The Fukushima Daiichi nuclear disaster of 2011 made it apparent that releases of fission products to marine environments is a very real possibility. Additional data on the movement of material through marine environments can be used by radioecology personnel to assist with both ecosystem protection as well as environmental cleanup...
    Resource Type:
    Masters Thesis
    Full Text:
    ........................................................................................................... 34 Appendix B: Gammavision Spectrum Report for 140 µl Sample of Cs-134

  • On the mechanism transition of power transient critical heat flux

    Creator:
    Yan, Yikuan
    Abstract:
    The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
    Resource Type:
    Dissertation
    Full Text:
    , no theoretical model has been made to describe the HSN process. The reason of the transition from

  • Heat Loss Characterization of NIST-1's Containment Vessel

    Creator:
    Yoshiura, Ramon K.
    Abstract:
    NuScale Power has designed a small modular reactor using natural circulation cooling dependent systems for both steady-state and transient operations. The NuScale Integral Test System (NIST-1) facility was built to supply test data to NuScale Power to verify and validate computer codes for the NuScale Power Mod- ule (NPM) with...
    Resource Type:
    Masters Thesis
    Full Text:
    , the simulation would be no longer an approximation but a validation processes in CFD terms. 7

  • Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

    Creator:
    Danielson, Jordan J.
    Abstract:
    All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing instruments are differential pressure sensing meters, which are invasive and could be the failure source in the pressure boundary of the primary coolant system. In...
    Resource Type:
    Masters Thesis
    Full Text:
    eliminated. This is advantageous because the primary system no longer has to rely on electricity being

  • Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems

    Creator:
    Somasundaram, Elanchezhian
    Abstract:
    The implementation of advanced hybrid (Monte Carlo/Deterministic) transport methods for realistic test problems has been a challenge due to the overhead efforts associated with interfacing a solution generated by a deterministic solver with a Monte Carlo based radiation transport code. In this work, with the help of Transpire, Inc., a...
    Resource Type:
    Dissertation
    Full Text:
    detector region and no particles can leak out of the system. The effective cross sections (Σt and Σs) for