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RISDevelopment and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The paper investigates the influence of the used thermal-hydraulic approximations on the coupled calculations of gas-cooled fast reactor design (hereby GFR 2400). The NESTLE code is used as coupled simulation tool and ...
Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The properties of nuclear fuel depend on the actual isotopic composition which develops during a reactor operation. In practice, the prediction accuracy of burnup calculations serves as the basis for the future precise ...
Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The scope of the current research in the field of fuel performance is primarily aimed at an improvement of the operating reliability, safety, and cost-effectiveness of the reactors in operation. The current requirement of ...