Global ETD Search

Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.

Results

Showing 1 to 4 of 4 for “"GEN IV Nuclear Reactor"”.

  1. Mean-Field Parameter Study of Radiation-Induced Segregation in a Binary Metal Alloy

    … pursuit of advanced materials for deployment in Generation IV (Gen-IV) nuclear reactor designs. A mean-field study is conducted on a body-centered cubic (BCC) A-B binary metal alloy system. The performance of the simulated metal system is measured by assessing the degree of segregation that …

    vt Repository record for Mean-Field Parameter Study of Radiation-Induced Segregation in a Binary Metal Alloy (opens in a new tab)

  2. Development of thermodynamic cycles for sodium-cooled-fast reactors.

    Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the thermal efficiencies reached by fossil-fired power plants, which are currently …

    uoit Repository record for Development of thermodynamic cycles for sodium-cooled-fast reactors. (opens in a new tab)

  3. Exposure and Characterization of Candidate Materials for Use in Supercritical Water Reactors

    … medium between a power source and the steam generating system lead to an increase in thermodynamic efficiency. Supercritical water systems have already been employed in fossil fuel power generation, and a proposed Gen IV nuclear reactor is designed to do the same which would result in an …

    unr Repository record for Exposure and Characterization of Candidate Materials for Use in Supercritical Water Reactors (opens in a new tab)

  4. Development of a coupled CFD—system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors

    Motivated by recent developments in the field of Computational Fluid Dynamics (CFD) and recognizing the limitations on computing power, this dissertation is aimed at combining the desirable features of system codes and CFD codes, thus elevating the nuclear reactor thermal hydraulics simulation …

    uiuc Repository record for Development of a coupled CFD—system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors (opens in a new tab)