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Showing 1 to 5 of 5 for “"Spent fuel cask"”.

  1. Allocation of spent nuclear fuel transport casks

    The selection of the form of spent nuclear fuel disposition, currently under debate, will precipitate an immediate requirement for spent-fuel transport regardless of the disposition alternative chosen. In this study, a constrained transportation model of the spent fuel cask scheduling problem is …

    vt Repository record for Allocation of spent nuclear fuel transport casks (opens in a new tab)

  2. Development and benchmarking of advanced FM-based particle transport algorithms for steady-state and transient conditions, implementation in RAPID and its VRS web-application

    … been successfully benchmarked against the GBC-32 spent fuel cask system, also highlighting issues with the standard eigenvalue Monte Carlo calculations that our code is capable of overcoming. A novel methodology for accounting for the movement of control rods in the JSI TRIGA reactor has been …

    vt Repository record for Development and benchmarking of advanced FM-based particle transport algorithms for steady-state and transient conditions, implementation in RAPID and its VRS web-application (opens in a new tab)

  3. Risk of misloading spent nuclear fuel cask for light water reactors

    The student, Ibrahim Jarrah, submitted this Thesis for approval on 2018-12-13 at 16:30.

    uiuc Repository record for Risk of misloading spent nuclear fuel cask for light water reactors (opens in a new tab)

  4. Thermal Behavior of the TN-32B Spent Nuclear Fuel Cask under Storage and Vacuum Drying Conditions

    … are developed to predict the temperatures in a spent fuel cask under storage and vacuum drying conditions. In particular, the TN-32 spent nuclear fuel cask was modeled because it is one of the few demonstration casks with publicly available experimental data to validate computational models for …

    unr Repository record for Thermal Behavior of the TN-32B Spent Nuclear Fuel Cask under Storage and Vacuum Drying Conditions (opens in a new tab)

  5. A novel framework for data-driven modeling, uncertainty quantification, and deep learning of nuclear reactor simulations

    … reactors, such as neutronics, reactor kinetics, fuel depletion, thermal-hydraulics, and fuel performance as well as outside the reactor such as spent fuel and criticality safety. The framework utilizes various computer models in the nuclear area, which are already validated and known to provide …

    uiuc Repository record for A novel framework for data-driven modeling, uncertainty quantification, and deep learning of nuclear reactor simulations (opens in a new tab)