Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors - Karahan, Aydin;Buongiorno, Jacopo;Kazimi, Mujid S.
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Nuclear fuel behavior modeling is an important piece of optimizing nuclear reactors. The first barrier against release of the radioactivity is the cladding material. A reliable tool is needed to assess the failure margin of this barrier during normal operation as well as accidental situations. To do it, a detailed micro-structural evolution of the fuel and the cladding, mechanical and chemical interaction between the fuel and cladding and the pressurization of the free volume of the fuel pin need to be modeled. The book presents an integrated model including fuel swelling, fission gas release,…mehr

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Produktbeschreibung
Nuclear fuel behavior modeling is an important piece of optimizing nuclear reactors. The first barrier against release of the radioactivity is the cladding material. A reliable tool is needed to assess the failure margin of this barrier during normal operation as well as accidental situations. To do it, a detailed micro-structural evolution of the fuel and the cladding, mechanical and chemical interaction between the fuel and cladding and the pressurization of the free volume of the fuel pin need to be modeled. The book presents an integrated model including fuel swelling, fission gas release, fuel constituent redistribution, cladding corrosion, straining and fracture for Sodium Fast Reactors.
Autorenporträt
Ayd¿n Karahan is a Research Scientist at Massachusetts Institute of Technology. He has extensive experience in modeling, simulation and optimization of the nuclear fission reactors. Dr. Karahan''s current interest is the multi-scale, multi-physics code development for the simulation of various nuclear reactors.