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Showing 1 to 5 of 5 for “"Reactor Coolant System"”.

  1. Estimate of radiation release for MIT research reactor during design basis accident

    … design basis accident at the MIT Research Reactor (MITR), radioactive fission products may be released from melted fuel plates into the con­tainment. To comply with regulations, the whole-body dose and thyroid dose at the boundary of the exclusion area as a result of this accident are …

    mit Repository record for Estimate of radiation release for MIT research reactor during design basis accident (opens in a new tab)

  2. Sensitivity analysis of the secondary heat balance at Koeberg Nuclear Power Station

    At Koeberg Nuclear Power Station, the reactor thermal power limit is one of the most important quantities specified in the operating licence, which is issued to Eskom by the National Nuclear Regulator (NNR). The reactor thermal power is measured using different methodologies, with the most …

    cape-town Repository record for Sensitivity analysis of the secondary heat balance at Koeberg Nuclear Power Station (opens in a new tab)

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

    … is aimed at combining the desirable features of system codes and CFD codes, thus elevating the nuclear reactor thermal hydraulics simulation capabilities to address problems that cannot be addressed with existing computational tools. The goal is achieved by first implementing improved porous …

    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)

  4. Spatio-temporal probabilistic methodology to estimate location-specific loss-of-coolant accident frequencies for risk-informed analysis of nuclear power plants

    … in nuclear regulatory activities. Since loss-of-coolant accidents (LOCAs) are critical initiating events for many PRA applications, the NRC has taken steps towards the quantification of LOCA frequencies for use in risk-informed applications. This research develops the Spatio-Temporal …

    uiuc Repository record for Spatio-temporal probabilistic methodology to estimate location-specific loss-of-coolant accident frequencies for risk-informed analysis of nuclear power plants (opens in a new tab)

  5. AI-based leakage prediction with uncertainty quantification and explainable AI for nuclear system

    Submission published under a 24 month embargo labeled 'Closed Access', the embargo will last until 2027-05-01

    uiuc Repository record for AI-based leakage prediction with uncertainty quantification and explainable AI for nuclear system (opens in a new tab)