Plastic Tensile Instability Analysis of Nuclear Fuel Rod Cracking
We performed analysis of plastic tensile instability conditions in pressurized cylindrical nuclear fuel rods, including the effects of biaxial stress and the instability modes of failure. The loss in strain hardening capacity of the material due to irradiation effects reduced the instability strains very substantially. Experimental fuel rod failure results were later found to be in excellent agreement with the theoretical predictions.
We Perform Engineering Analysis on Various Nuclear Power Plant Components.
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Related Projects
– Finite Element Analysis & ASME Code Section VIII Division 2 Calculations on Feedwater Heaters
– Developments of Elevated Temperature Design Criteria for Nuclear Components
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– Design & Analysis
– Nuclear Power Plant Consulting
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– Publications – Heat Exchangers, Pressure Vessels, Welds, Fatigue, Elevated Temperature
– Links to Engineering Resources
– Our Engineering Team
– Background of the ASME Code