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file = {Michael F. Simpson - 2012 - Developments of Spent Nuclear Fuel Pyroprocessing .pdf:C\:\\Users\\Greg\\Zotero\\storage\\EV7K6DRE\\Michael F. Simpson - 2012 - Developments of Spent Nuclear Fuel Pyroprocessing .pdf:application/pdf;Michael F. Simpson - 2012 - Developments of Spent Nuclear Fuel Pyroprocessing .pdf:C\:\\Users\\Greg\\Zotero\\storage\\8H7TFITG\\Michael F. Simpson - 2012 - Developments of Spent Nuclear Fuel Pyroprocessing .pdf:application/pdf}
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@article{li_electrorefining_2005,
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title = {Electrorefining {Experience} for {Pyrochemical} {Processing} of {Spent} {EBR}-{II} {Driver} {Fuel}},
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abstract = {Pyrochemical processing has been implemented for the treatment of spent fuel from the Experimental Breeder Reactor-II (EBR-II) at Idaho National Laboratory since 1996. This report summarizes technical advancements made in electrorefining of spent EBR-II driver fuel in the Mk-IV electrorefiner since the pyrochemical processing was integrated into the AFCI program in 2002. The significant advancements include improving uranium dissolution and noble metal retention from chopped fuel segments, increasing cathode current efficiency, and achieving co-collection of zirconium along with uranium from the cadmium pool.},
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language = {en},
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number = {487},
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author = {Li, Shelly X and Johnson, Thomas A and Westphal, Brian R and Goff, Kenneth M and Benedict, Robert W},
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year = {2005},
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pages = {7},
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file = {Li et al. - 2005 - Electrorefining Experience for Pyrochemical Proces.pdf:C\:\\Users\\Greg\\Zotero\\storage\\2T24SP52\\Li et al. - 2005 - Electrorefining Experience for Pyrochemical Proces.pdf:application/pdf}
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}
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@article{lee_determination_2012,
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title = {Determination of the {Plutonium} {Mass} and {Curium} {Ratio} of {Spent} {Fuel} {Assemblies} for {Input} {Nuclear} {Material} {Accountancy} of {Pyroprocessing}, and {Analysis} of {Their} {Errors}},
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volume = {179},
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issn = {0029-5450},
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url = {https://doi.org/10.13182/NT11-77},
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doi = {10.13182/NT11-77},
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abstract = {In pyroprocessing it is important to determine the amount of Pu in the various streams of materials involved. This paper presents two approaches to determine the Pu mass of spent fuel assemblies using nondestructive assay and burnup simulation code. Cm balance is adopted and the concept of “Cm ratio,” the mass ratio of Pu to Cm, is used for the nuclear material accountancy for the model pyroprocessing facility. The biggest error of the nuclear material accountancy is expected to arise from the determination of Pu mass and Cm ratio in input homogeneously mixed uranium oxide powder, which is assayed nondestructively. One approach to determine the Pu mass and Cm ratio is to apply the average burnup of spent fuel and determine the Pu mass and Cm ratio by using the ORIGEN code. The estimated error in Pu mass determined by this method ranges from 0.94\% to 2.33\% for a total of 225 spent fuel assemblies of various burnup, initial enrichment, and cooling time. The other approach is to use the functional relationship between the neutron emission rate and Pu mass of spent fuel. The error in Pu mass calculated using this method ranges from -1.68\% to 3.86\%.},
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number = {2},
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urldate = {2019-10-23},
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journal = {Nuclear Technology},
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author = {Lee, Tae-Hoon and Kim, Young-Soo and Kwon, Tae-Je and Shin, Hee-Sung and Kim, Ho-Dong},
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