T
Troy G. Garn
Researcher at Idaho National Laboratory
Publications - 50
Citations - 464
Troy G. Garn is an academic researcher from Idaho National Laboratory. The author has contributed to research in topics: Spent nuclear fuel & Contactor. The author has an hindex of 8, co-authored 49 publications receiving 376 citations. Previous affiliations of Troy G. Garn include Battelle Memorial Institute.
Papers
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Journal ArticleDOI
Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities
Nick Soelberg,Troy G. Garn,Mitchell R. Greenhalgh,Jack D. Law,Robert Thomas Jubin,Denis M. Strachan,Praveen K. Thallapally +6 more
TL;DR: The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessed facility in the United States as discussed by the authors.
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Polyacrylonitrile-chalcogel hybrid sorbents for radioiodine capture.
Brian J. Riley,David A. Pierce,Jaehun Chun,Josef Matyas,William C. Lepry,Troy G. Garn,Jack D. Law,Mercouri G. Kanatzidis +7 more
TL;DR: X-ray diffraction results showed the formation of crystalline SnI 4 and SnI4(S8)2, revealing that the iodine binding in these materials is mainly due to a chemisorption process, although a small amount of physisor adaptation was observed.
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Some aspects of fundamental chemistry of the Universal Extraction (UNEX) process for the simultaneous separation of major radionuclides (cesium, strontium, actinides, and lanthanides) from radioactive wastes
Thomas A. Luther,R. S. Herbst,Dean R. Peterman,Richard D. Tillotson,Troy G. Garn,Vasily Babain,Igor V. Smirnov,Evgenii S. Stoyanov,N. G. Antonov +8 more
TL;DR: In this paper, a Universal Extraction (UNEX) process for simultaneously removing the major radionuclides (Cs, Sr, actinides, and lanthanides) from acidic radioactive waste in a single solvent extraction process is presented.
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Pilot-Scale TRUEX Flowsheet Testing for Separation of Actinides and Lanthanides from used Nuclear Fuel
TL;DR: In this paper, a TRUEX flowsheet has been tested using a thirty-stage, 5-cm centrifugal contactor pilot plant using a non-radioactive feed surrogate and data were collected and analyzed to evaluate removal efficiencies of the lanthanides.
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The solvent extraction of Am(VI) using centrifugal contactors
Bruce J. Mincher,Richard D. Tillotson,Troy G. Garn,Veronica Rutledge,Jack D. Law,Nicholas C. Schmitt +5 more
TL;DR: An engineering-scale contactor test bed was built at Idaho National Laboratory to perform solvent extraction testing for the partitioning of hexavalent americium as mentioned in this paper, where raffinate simulant feed was spiked with 243Am and 139Ce and treated with sodium bismuthate to oxidize americium to Am(VI), filtered and contacted with 1 M DAAP/dodecane using centrifugal contactors.