22_314_quiz - Department of Nuclear Engineering 22.314 :...

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Department of Nuclear Engineering 22.314 : Structural Mechanics In Nuclear PowerTechnology Quiz No.1 Fall Term 2006 Open Book, 1.5 hours Please state your assumptions and the definition of symbols appearing in your equations clearly. Note that there is an opportunity to get a score over 100 if you solve all questions correctly. Question #1 (45%) For future sodium-cooled reactors, uranium carbide may be used as fuel. The fuel pin will be of cylindrical geometry and housed in a stainless steel clad. The dimensions as well as the physical and mechanical properties of the fuel material and the clad are given in Table 1. 1.1 What is the maximum linear hear generation rate (in kW/m) that the fuel pin can operate at if the fuel is not to experience any fracture for r < 0.4R, where R is the pellet radius? You may assume the pressure at the pellet- clad gap to be 0.3 MPa. 1.2 Does the clad design satisfy the ASME criteria for structural integrity under static loads? The fission gases will build up within the clad until the
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22_314_quiz - Department of Nuclear Engineering 22.314 :...

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