Simulation of uranium mononitride spent fuel: A crystallographic approach
نویسندگان
چکیده
Uranium mononitride (UN) is an attractive fuel for a range of reactors, including, with adequate protection against reaction water, large scale and small modular light water reactors. The study the speciation fission products (Fps) in spent UN required to understand their properties such as phase stability retention during long term storage disposal. present reviews applies Hume-Rothery rules predict this speciation. This law provides estimate way may form solid solutions actinide (An) product mononitrides from Beginning Life (BoL) End (EoL). Composition at EoL estimated high burnup (60 MW d kg−1) using FISPIN inventory code. Many Fps are trivalent (Ln, Y, Zr, Nb) expected recrystallize face centred cubic (fcc) UN. Other divalent (Ba, Sr) monovalent (Cs, Rb) some elements non-valent (Mo, Tc, Ru, Rh, Pd) well noble gases (Xe, Kr), halides (I, Br) which nano-precipitates. Actinides formed by neutron capture 238U all An3+ also found fcc solution consequently fraction soluble nitrides (U, An, Ln, Nb)N forming single rather homogeneous according rules. will follow Vegard's law. Because low temperature fuel, be or nano-dispersed precipitates. Microscopic precipitated phases not expected.
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ژورنال
عنوان ژورنال: Journal of Nuclear Materials
سال: 2022
ISSN: ['1873-4820', '0022-3115']
DOI: https://doi.org/10.1016/j.jnucmat.2022.153612