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Showing 1 to 6 of 6 for “"Generation IV nuclear reactors"”.

  1. Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system

    Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other …

    mit Repository record for Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system (opens in a new tab)

  2. Dynamic response of the supercritical C0₂ Brayton recompression cycle to various system transients

    … has been suggested for use with many of the Generation IV nuclear reactors. The SC0₂ cycle is highly attractive because of its low operating temperatures and high efficiency associated with working near the critical point of CO2. Unfortunately, the appealing features of using C0₂ near its …

    mit Repository record for Dynamic response of the supercritical C0₂ Brayton recompression cycle to various system transients (opens in a new tab)

  3. Power conversion system design for supercritical carbon dioxide cooled indirect cycle nuclear reactors

    … conversion cycle which couples nicely to many Generation IV nuclear reactors. This work investigates the power conversion system design and proposes several "Third Generation" plant layouts for power ratings ranging between 20 and 1200 MWe for the recompression cycle. A 20 MWe simple cycle …

    mit Repository record for Power conversion system design for supercritical carbon dioxide cooled indirect cycle nuclear reactors (opens in a new tab)

  4. Numerical Investigations of the Fluid Flow and Heat Transfer and Construction of Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant

    Canada participated in the Generation IV nuclear reactors with the Supercritical Water-Cooled Reactor (SCWR) concept. This work focuses on the numerical studies of the fluid flow and heat transfer of the supercritical water in the nuclear reactor fuel bundle, and the construction of the linear …

    uwo Repository record for Numerical Investigations of the Fluid Flow and Heat Transfer and Construction of Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant (opens in a new tab)

  5. Effect of helium, strontium and silver implanted into silicon carbide on the structural changes and migration of the implants

    Containment of radioactive fission products (FPS) is a cornerstone in the revival of nuclear reactors as a clean energy source. In modern generation IV nuclear reactors, safety is enhanced by coating the fuel kernel with four layers of chemical vapour deposited carbon and silicon carbide (SiC). The …

    pretoria Repository record for Effect of helium, strontium and silver implanted into silicon carbide on the structural changes and migration of the implants (opens in a new tab)

  6. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications

    … to those for proposed SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, this new correlation, for forced convective heat transfer in the normal heat-transfer regime, can be used for preliminary heat-transfer calculations in SCWR fuel channels. It has demonstrated a good fit for …

    uoit Repository record for Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications (opens in a new tab)