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dc.contributor.authorWang, Lian-Cheng
dc.contributor.authorKaye, Matthew H.
dc.date.accessioned2022-02-05T21:51:39Z
dc.date.available2022-02-05T21:51:39Z
dc.date.copyright10/1/2020 12:00:00 AM
dc.date.issued2020
dc.identifier.issn2332-8983
dc.identifier.otherners_007_01_011601.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276475
dc.description.abstractDuring burnup of nuclear fuel, fission products accumulate. Post-irradiation examination of burned up nuclear fuel has revealed the presence of several phases, namely, the fuel matrix of UO2, with dissolved oxides present; a white metallic phase consisting of the so-called “noble metals” (i.e., Mo–Ru–Pd–Rh–Tc); a gray oxide phase consisting of alkali or alkaline earth oxides (e.g., BaZrO3 or Cs2UO4); and an another metallic inclusion containing a mixture of UPd3–URh3–URu3, which is not completely assessed due to the lack of phase diagrams of the UPd3–URh3, URh3–URu3, and UPd3–URu3. Understanding how these phases behave becomes especially important from a safety perspective, if one considers a potential accident scenario. The quaternary system U–Pd–Rh–Ru has been evaluated and a thermodynamic model has been developed by first considering the six binary subsystems and the four ternary subsystems. A critical examination of the U–Pd, U–Rh, and U–Ru experimental phase diagrams has been made, with attention placed on both the solution phases, generally present on the uranium side of the diagrams and the UPd3–URh3–URu3 compounds. Finally, the implications of this new model and its potential refinements of the Royal Military College of Canada nuclear fuel treatment developed by previous authors (notably the RMCC group under Thompson and Lewis) will be explored.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleThe Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
dc.typeJournal Paper
dc.journal.volume7
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4046784
dc.journal.fristpage011601-1
dc.journal.lastpage011601-10
dc.page10
dc.treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 007 ):;issue: 001
dc.contenttypeFulltext


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