Modelling of Nuclear Fuel Behavior
Nuclear fuel in-reactor behavior is subject to great number of physical and chemical processes that take place during irradiation of the nuclear fuel elements. The practical difficulties with long term experimental investigation of in-reactor fuel rods were a major drawback in evaluating the influence of the main fuel rod design and operational parameters on its performance. Fuel performance simulation models and codes have been developed by nuclear fuel vendors, utility organizations and national laboratories, mainly during the 1970s and 1980s. Along this, well characterized experimental database for code validations was created. With increasing of the max fuel burnup, introduction of new advanced nuclear fuel materials and reactor power upgrading additional analytical needs have emerged in recent years.

Modeling of the nuclear fuel behavior under normal operation up to high burnup and during transient, and accident conditions provides information about integrity of nuclear fuel and nuclear reactor safety .The presentation discusses the models and codes employed for modeling of nuclear fuel performance in steady state and off-normal conditions. The following groups of models utilized in advanced nuclear fuel behavior computer codes are presented: Thermal-hydraulics, thermal, thermo-mechanical and nuclear irradiation. Special attention is paid to modeling of materials properties and physical phenomena, which take place in the nuclear fuel during irradiation. Presented comparisons between nuclear fuel codes predictions and experimental data shows good agreement for specific reactor conditions.

June 14, 2007 at 10:00AM in Bldg. 208/A138

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See also: RERTR Program - RERTR website

Printable version of this abstract: Modelling of Nuclear Fuel Behavior.

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