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Xiangzhe Kong,Shurong Ding,Hongyan Yang,Xiaoming Peng 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.8
High-density UMo/Zr monolithic nuclear fuel plates have a promising application prospect in high fluxresearch and test reactors. The solid state welding method called co-rolling is used for their fabrication. Hot co-rolling simulations for the composite blanks of UMo/Zr monolithic nuclear fuel plates are performed. The effects of coupon sizes and mechanical property parameters on the contact pressures betweenthe to-be-bonded surfaces are investigated and analyzed. The numerical simulation resultsindicate that 1) the maximum contact pressures between the fuel coupon and the Zircaloy cover existnear the central line along the plate length direction; as a whole the contact pressures decrease towardthe edges in the plate width direction; and lower contact pressures appear at a large zone near thecoupon corner, where de-bonding is easy to take place in the in-pile irradiation environments; 2) themaximum contact pressures between the fuel coupon and the Zircaloy parts increase with the initialcoupon thickness; after reaching a certain thickness value, the contact pressures hardly change, whichwas mainly induced by the complex deformation mechanism and special mechanical constitutive relationof fuel coupon; 3) softer fuel coupon will result in lower contact pressures and form interfaces beingmore out-of-flatness.
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Xiaobin Jian,Xiangzhe Kong,Shurong Ding 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.6
Fracture near the Ue10Mo/cladding material interface impacts fuel service life. In this work, a mesoscalestress model is developed with the fuel foil considered as a porous medium having gas bubbles andbearing bubble pressure and surface tension. The models for the evolution of bubble volume fraction,size and internal pressure are also obtained. For a Ue10Mo/Al monolithic fuel plate under locationdependentirradiation, the finite element simulation of the thermo-mechanical coupling behavior isimplemented to obtain the bubble distribution and evolution behavior together with their effects on themesoscale stresses. The numerical simulation results indicate that higher macroscale tensile stressesappear close to the locations with the maximum increments of fuel foil thickness, which is intensivelyrelated to irradiation creep deformations. The maximum mesoscale tensile stress is more than 2 times ofthe macroscale one on the irradiation time of 98 days, which results from the contributions of considerablevolume fraction and internal pressure of bubbles. This study lays a foundation for the fracturemechanism analysis and development of a fracture criterion for Ue10Mo monolithic fuels.
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