![]() The limitation of this path is that codes are often restricted to the end user because they have hardcoded functionality. Fuel modeling codes are commonly built as isolated computer software. These codes usually apply several correlations with fixed coupling among the different phenomena. These multiphysics performances inextricably link the mechanical, thermal, and chemical phenomena, which are linked with many control parameters and associated uncertainties.Įarly fuel modeling codes used a one-dimensional or asymmetrical-two-dimensional description for the fuel geometry, such as GAPCON, FEMAXI, FALCON, FRAPCON, and FRAPTRAN. Nuclear fuel performance codes are necessary because of the difficulty and high cost of nuclear experimental measurements. Understanding and predicting the evolution of nuclear fuel properties are necessary for fuel design, operational behavior, and long-term storage. Studies that have attempted to understand the irradiation behavior of fuels in nuclear reactors have found considerable alterations in the geometry, dimensions, composition, and microstructure of fuels during and after irradiation. Nuclear fuels are exposed to highly challenging harsh operational conditions in the reactor core, where corrosive media, mechanical stresses, and high temperatures are combined with intensive radiation effects on fuel elements. Although the model was developed for normal operating conditions, it can be modified to include off-normal operating conditions. A compilation of related material and thermomechanical models was conducted and included in the modeling to allow the user to investigate different material/performance models. The model was then used to predict the VVER-1200 fuel performance parameters as a function of burnup, including the temperature profiles, gap width, fission gas release, and plenum pressure. A sensitivity study was also conducted to assess the effects of uncertainty on some of the model parameters. This prediction proved that the model could perform according to previously published VVER nuclear fuel performance parameters. The model was validated using a code-to-code evaluation of the fuel pellet centerline and surface temperatures in the case of constant power, in addition to validation of fission gas release (FGR) predictions. The modeling considers all relevant phenomena, including heat generation and conduction, gap heat transfer, elastic strain, mechanical contact, thermal expansion, grain growth, densification, fission gas generation and release, fission product swelling, gap/plenum pressure, and cladding thermal and irradiation creep. The modeling was performed for a 2D axis-symmetric geometry of a UO 2 fuel pellet in the E110 clad for VVER-1200 fuel. In this study, a fuel performance model was developed using the COMSOL Multiphysics platform. ![]() ![]() Fuel performance is a complicated phenomenon that involves thermal, mechanical, and irradiation mechanisms and requires special multiphysics modules. Nuclear fuel performance modeling and simulation are critical tasks for nuclear fuel design optimization and safety analysis under normal and transient conditions.
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