text:
@article{lee_korean_2011,
	title = {Korean {Pyrochemical} {Process} {R}\&{D} activities},
	volume = {7},
	issn = {18766102},
	url = {http://linkinghub.elsevier.com/retrieve/pii/S1876610211015608},
	doi = {10.1016/j.egypro.2011.06.051},
	language = {en},
	urldate = {2018-03-11},
	journal = {Energy Procedia},
	author = {Lee, Hansoo and Hur, Jin-Mok and Kim, Jeong-Guk and Ahn, Do-Hee and Cho, Yung-Zun and Paek, Seong-Woo},
	year = {2011},
	pages = {391--395},
	file = {Lee et al. - 2011 - Korean Pyrochemical Process R&D activities.pdf:C\:\\Users\\Greg\\Zotero\\storage\\QAP5PXQA\\Lee et al. - 2011 - Korean Pyrochemical Process R&D activities.pdf:application/pdf}
}

@article{borrelli_approaches_2017,
	title = {Approaches to a Practical Systems Assessment for Safeguardability of Advanced Nuclear Fuel Cycles},
	volume = {197},
	journal = {Nuclear Technology},
	author = {Borrelli, R. A. and Ahn, J. and Hwang, Y.},
	month = mar,
	year = {2017},
	pages = {248--264}
}

@article{lee_advanced,
	title = {Advanced {Electrorefining} {Process} at {KAERI}},
	url = {http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/40/032/40032685.pdf},
	abstract = {In order to enhance the throughput of a pyroprocessing in which electrochemical processes are
mostly engaged, the design of a continuous concept is required. The graphite cathode in the electrorefiner
enables the uranium deposit on the cathodes to be stripped off spontaneously, resulting in a continuous
reaction. The collected uranium deposits at the bottom of the inner cone of the reactor are transferred by a
conveyer. The residuals in the anode basket after the uranium is depleted are noble metals. These are also
collected at the bottom of the outer shell of the reactor, and conveyed from the reactor for a further
treatment. This work addresses the design of the electrorefiner for a continuous operation. The behavior
of particles such as uranium dendrites or noble metals was analyzed to achieve the proper operating
conditions. The operating conditions for the cathode processor in which molten salt is distilled were also
investigated.},
	urldate = {2018-03-09},
	journal = {ATALANTE},
	author = {Lee, Hansoo and Lee, Jong Hyun and Park, Sung Bin and Lee, Yoon Sang and Kim, Eung Ho and Park, Sung Won},
	month = may,
	year = {2008},
	file = {40032685.pdf:C\:\\Users\\Greg\\Zotero\\storage\\FJ2GXPWT\\40032685.pdf:application/pdf}
}

@article{herrmann_separation_2010,
	title = {Separation and {Recovery} of {Uranium} {Metal} from {Spent} {Light} {Water} {Reactor} {Fuel} {Via} {Electrolytic} {Reduction} and {Electrorefining}},
	volume = {171},
	issn = {0029-5450, 1943-7471},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT171-247},
	doi = {10.13182/NT171-247},
	language = {en},
	number = {3},
	urldate = {2018-03-14},
	journal = {Nuclear Technology},
	author = {Herrmann, S. D. and Li, S. X.},
	month = sep,
	year = {2010},
	pages = {247--265},
	file = {Herrmann and Li - 2010 - Separation and Recovery of Uranium Metal from Spen.pdf:C\:\\Users\\Greg\\Zotero\\storage\\VHBCE393\\Herrmann and Li - 2010 - Separation and Recovery of Uranium Metal from Spen.pdf:application/pdf}
}

@article{choi_electrochemical_2015,
	title = {Electrochemical processing of spent nuclear fuels: {An} overview of oxide reduction in pyroprocessing technology},
	volume = {25},
	issn = {10020071},
	shorttitle = {Electrochemical processing of spent nuclear fuels},
	url = {http://linkinghub.elsevier.com/retrieve/pii/S1002007115001197},
	doi = {10.1016/j.pnsc.2015.11.001},
	abstract = {The electrochemical reduction process has been used to reduce spent oxide fuel to a metallic form using pyroprocessing technology for a closed fuel cycle in combination with a metal-fuel fast reactor. In the electrochemical reduction process, oxides fuels are loaded at the cathode basket in molten Li2O–LiCl salt and electrochemically reduced to the metal form. Various approaches based on thermodynamic calculations and experimental studies have been used to understand the electrode reaction and efﬁciently treat spent fuels. The factors that affect the speed of the electrochemical reduction have been determined to optimize the process and scale-up the electrolysis cell. In addition, demonstrations of the integrated series of processes (electroreﬁning and salt distillation) with the electrochemical reduction have been conducted to realize the oxide fuel cycle. This overview provides insight into the current status of and issues related to the electrochemical processing of spent nuclear fuels.},
	language = {en},
	number = {6},
	urldate = {2018-03-14},
	journal = {Progress in Natural Science: Materials International},
	author = {Choi, Eun-Young and Jeong, Sang Mun},
	month = dec,
	year = {2015},
	pages = {572--582},
	file = {Choi and Jeong - 2015 - Electrochemical processing of spent nuclear fuels.pdf:C\:\\Users\\Greg\\Zotero\\storage\\EJZJMZNK\\Choi and Jeong - 2015 - Electrochemical processing of spent nuclear fuels.pdf:application/pdf}
}

@article{organisation,
	title = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	shorttitle = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	url = {https://www.oecd-nea.org/science/docs/2012/nsc-wpfc-doc2012-15.pdf},
	language = {en},
	urldate = {2018-03-14},
	journal = {Nuclear Energy Agency},
	author = {{Organisation for Economic Co-operation and Development}},
	month = jun,
	year = {2012},
	file = {Organisation for Economic Cooperation and Development - 1998 - Organisation for economic cooperation and developm.pdf:C\:\\Users\\Greg\\Zotero\\storage\\LTWXQPK6\\Organisation for Economic Cooperation and Development - 1998 - Organisation for economic cooperation and developm.pdf:application/pdf}
}

@article{kim_development_2013,
	title = {Development of an anode structure consisting of graphite tubes and a {SiC} shroud for the electrowinning process in molten salt},
	volume = {295},
	issn = {0236-5731, 1588-2780},
	url = {http://link.springer.com/10.1007/s10967-012-2103-5},
	doi = {10.1007/s10967-012-2103-5},
	abstract = {In a molten chloride salt-based electrolysis, chloride evolution at an anode needs to be considered in terms of potential ﬂuctuation, capture, and corrosion problems. Here, we demonstrate an anode structure consisting of graphite tubes and a SiC shroud to be applied to the electrowinning process. A large surface area as well as high corrosion resistivity was achieved through the use of inert graphite tubes. The Cl2 (g) capture was enhanced by the employment of a porous SiC shroud. It also allows an efﬁcient contact of the electrode surface to the LiCl–KCl eutectic melt for an anodic evolution. No signiﬁcant effects of the use of a SiC shroud on the anode overpotential and cell potential were found during the U deposition test.},
	language = {en},
	number = {3},
	urldate = {2018-04-27},
	journal = {Journal of Radioanalytical and Nuclear Chemistry},
	author = {Kim, Tack-Jin and Kim, Gha-Young and Yoon, Dalseong and Ahn, Do-Hee and Paek, Seungwoo},
	month = mar,
	year = {2013},
	pages = {1855--1859},
	file = {Kim et al. - 2013 - Development of an anode structure consisting of gr.pdf:C\:\\Users\\Greg\\Zotero\\storage\\3UUDYXM2\\Kim et al. - 2013 - Development of an anode structure consisting of gr.pdf:application/pdf}
}

@techreport{jubin_spent_2009,
	title = {Spent {Fuel} {Reprocessing}},
	url = {http://www.cresp.org/NuclearChemCourse/monographs/07_Jubin_Introduction%20to%20Nuclear%20Fuel%20Cycle%20Separations%20-%20Final%20rev%202_3_2_09.pdf},
	urldate = {2018-05-04},
	institution = {Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)},
	author = {Jubin, Robert},
	year = {2009},
	file = {07_Jubin_Introduction to Nuclear Fuel Cycle Separations - Final rev 2_3_2_09.pdf:C\:\\Users\\Greg\\Zotero\\storage\\AVVWXH3N\\07_Jubin_Introduction to Nuclear Fuel Cycle Separations - Final rev 2_3_2_09.pdf:application/pdf}
}

@article{ohta,
	title = {Pyroprocessing of {Light} {Water} {Reactor} {Spent} {Fuels} {Based} on an {Electrochemical} {Reduction} {Technology}},
	volume = {150},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT05-A3613},
	doi = {10.13182/NT05-A3613},
	abstract = {A concept of pyroprocessing light water reactor (LWR) spent fuels based on an electrochemical reduction technology is proposed, and the material balance of the processing of mixed oxide (MOX) or high-burnup uranium oxide (UO2) spent fuel is evaluated. Furthermore, a burnup analysis for metal fuel fast breeder reactors (FBRs) is conducted on low-decontamination materials recovered by pyroprocessing. In the case of processing MOX spent fuel (40 GWd/t), UO2 is separately collected for 60 wt\% of the spent fuel in advance of the electrochemical reduction step, and the product recovered through the rare earth (RE) removal step, which has the composition uranium:plutonium:minor actinides:fission products (FPs) = 76.4:18.4:1.7:3.5, can be applied as an ingredient of FBR metal fuel without a further decontamination process. On the other hand, the electroreduced alloy of high-burnup UO2 spent fuel (48 GWd/t) requires further decontamination of residual FPs by an additional process such as electrorefining even if RE FPs are removed from the alloy because the recovered plutonium (Pu) is accompanied by almost the same amount of FPs in addition to RE. However, the amount of treated materials in the electrorefining step is reduced to 10 wt\% of the total spent fuel owing to the prior UO2 recovery step. These results reveal that the application of electrochemical reduction technology to LWR spent oxide fuel is a promising concept for providing FBR metal fuel by a rationalized process.},
	number = {2},
	urldate = {2018-12-13},
	journal = {Nuclear Technology},
	author = {Ohta, Hirokazu and Inoue, Tadashi and Sakamura, Yoshiharu and Kinoshita, Kensuke},
	month = may,
	year = {2005},
	pages = {153--161},
	file = {Full Text PDF:/home/gtw2/Zotero/storage/ZRDKP2MM/Ohta et al. - 2005 - Pyroprocessing of Light Water Reactor Spent Fuels .pdf:application/pdf;Snapshot:/home/gtw2/Zotero/storage/TETSAVEY/NT05-A3613.html:text/html}
}

@article{hur_electrochemical_nodate,
	title = {Electrochemical {Reduction} of {Uranium} {Oxides} in {Li}2O-{LiCl} {Molten}-salt},
	abstract = {A concept of electrochemical reduction of spent oxide fuel in Li2O-LiCl molten-salt was proposed and several cold tests using fresh uranium oxides have been carried out at KAERI. In this new electrochemical reduction process, electrolysis of Li2O and reduction of uranium oxide are taking place simultaneously at the cathode part of electrolysis cell. Li produced via Li2O electrolysis reacts with uranium oxide resulting in the formation of Li2O of which oxygen ion originates from uranium oxide. The resultant Li2O is electrolysed and regenerated Li is used for further reduction of the uranium oxide. The cathode part consisted of uranium oxide, stainless steel conductor, and a nonconductive porous magnesia filter. The conversion of uranium oxide to uranium metal reached more than 99\% and closed recycle of Li2O was elucidated by the observation of its concentration variation in molten-salt.},
	language = {en},
	month = jan,
	year = {2010},
	author = {Hur, J-M and Seo, C-S and Hong, S-S and Kang, D-S and Park, S-W},
	pages = {7},
	file = {Hur et al. - Electrochemical Reduction of Uranium Oxides in Li2.pdf:/home/gtw2/Zotero/storage/I4LFEACR/Hur et al. - Electrochemical Reduction of Uranium Oxides in Li2.pdf:application/pdf}
}

@inproceedings{phongikaroon_introduction_2015,
	address = {Online},
	type = {Webinar},
	title = {Introduction to {Pyroprocessing} {Technology} for {Used} {Nuclear} {Fuel}},
	language = {en},
	author = {Phongikaroon, Supathorn},
	month = mar,
	year = {2015},
	publisher = {National Analytical Management Program},
	file = {Phongikaroon_2015_Introduction to Pyroprocessing Technology for Used Nuclear Fuel.pdf:C\:\\Users\\Greg\\Zotero\\storage\\2LGCYVHA\\Phongikaroon_2015_Introduction to Pyroprocessing Technology for Used Nuclear Fuel.pdf:application/pdf}
}

@inproceedings{westphal_pyre_2018,
	address = {Orlando, FL},
	title = {{PyRe}: {A} {Cyclus} {Pyroprocessing} {Facility} {Archetype}},
	publisher = {ANS},
	author = {Westphal, Greg},
	month = nov,
	year = {2018}
}

@book{angel,
	title = {Chemistry: {The} {Central} {Science}, 11th ed.},
	isbn = {978-0-321-58561-5},
	shorttitle = {Chemistry},
	language = {English},
	publisher = {Prentice Hall},
	author = {Brown, Theodore E. and LeMay, H. Eugene H. and Bursten, Bruce E. and Murphy, Catherine and Woodward, Patrick},
	month = jul,
	year = {2008}
}

@article{sakamura,
	title = {Separation of {Actinides} from {Rare} {Earth} {Elements} by {Electrorefining} in {LiCl}-{KCl} {Eutectic} {Salt}},
	volume = {35},
	number = {1},
	journal = {J. Nucl. Sci. Technol.},
	author = {Sakamura, Y.},
	month = jan,
	year = {1998},
	pages = {49--59}
}

@article{organisation_for_economic_cooperation_and_development_spent_2012,
	title = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	shorttitle = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	url = {https://www.oecd-nea.org/science/docs/2012/nsc-wpfc-doc2012-15.pdf},
	language = {en},
	urldate = {2018-03-14},
	journal = {Nuclear Energy Agency},
	author = {{Organisation for Economic Cooperation and Development}},
	month = jun,
	year = {2012}
}

@article{chapman_revision_1984,
	title = {Revision of the uranium-iron phase diagram},
	volume = {126},
	issn = {00223115},
	url = {http://linkinghub.elsevier.com/retrieve/pii/0022311584900461},
	doi = {10.1016/0022-3115(84)90046-1},
	language = {en},
	number = {3},
	urldate = {2018-04-03},
	journal = {Journal of Nuclear Materials},
	author = {Chapman, L.R. and Holcombe, C.E.},
	month = nov,
	year = {1984},
	pages = {323--326}
}

@article{herrmann_separation_2010,
	title = {Separation and {Recovery} of {Uranium} {Metal} from {Spent} {Light} {Water} {Reactor} {Fuel} {Via} {Electrolytic} {Reduction} and {Electrorefining}},
	volume = {171},
	issn = {0029-5450, 1943-7471},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT171-247},
	doi = {10.13182/NT171-247},
	language = {en},
	number = {3},
	urldate = {2018-03-14},
	journal = {Nuclear Technology},
	author = {Herrmann, S. D. and Li, S. X.},
	month = sep,
	year = {2010},
	pages = {247--265}
}

@article{koyama_development_2012,
	title = {Development of {Pyro}-processing {Fuel} {Cycle} {Technology} for {Closing} {Actinide} {Cycle}},
	volume = {7},
	issn = {18766196},
	url = {http://linkinghub.elsevier.com/retrieve/pii/S187661961200191X},
	doi = {10.1016/j.proche.2012.10.117},
	abstract = {Pyro-processing fuel cycle technology is a promising technological candidate to realize advanced fuel cycle with reduced burdens of proliferation risk and long life radioactive waste. CRIEPI have been studying pyro-processing and metal fuel technology since 1986 for obtaining basic properties, process chemistry and engineering technologies. In this century, CRIEPI and JRC-ITU have jointly demonstrated the recovery of MAs from both irradiated metal fuels and spent MOX fuels. Since 2009, accumulation of the design basics through tests with engineering-scale pyroprocessing equipment is carried out by CRIEPI. According to the results obtained in these studies, feasibility of pyroprocessing fuel cycle technology was evaluated through estimation of Technology Readiness Level and cycle cost based on the design study of fuel cycle facility of 40 tonHM/y throughput.},
	language = {en},
	urldate = {2018-03-11},
	journal = {Procedia Chemistry},
	author = {Koyama, T. and Sakamura, Y. and Iizuka, M. and Kato, T. and Murakami, T. and Glatz, J.-P.},
	year = {2012},
	pages = {772--778}
}

@misc{noauthor_serving_2017,
	title = {Serving {Nuclear} {Non}-{Proliferation}},
	author = {Yukiya Amano},
	url = {https://www.iaea.org/sites/default/files/17/12/sg-serving-nuclear-non-proliferation.pdf},
	urldate = {2018-05-05},
	publisher = {IAEA},
	year = {2017}
}

@techreport{ando_estimation_1999,
	address = {Tokai Research Establishment},
	title = {Estimation of {LWR} {Spent} {Fuel} {Composition}},
	url = {http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/30/019/30019847.pdf?r=1},
	abstract = {In the nuclear transmutation reactor, minor actinide (MA) and fission product (FP) included in
high-level waste solution after the reprocessing of spent fuels from the nuclear power plant are transmuted with the nuclear power production.
In future, MA and FP compositions in spent fuels will be diversified with the use of high discharged burnup fuels and MOX fuels in LWRs (BWRs and PWRs) taking a leading part of power
reactors.
In this report, compositions of various LWR spent fuels (discharged burnup :33, 45 and 60GWd/
tHM, fuel type :UO2 and MOX) are estimated by the burnup calculation code system SWAT and
studied by the comparison among various forms of fuels and cooling periods.},
	number = {99-004},
	urldate = {2018-04-17},
	institution = {JAERI},
	author = {Ando, Yoshihira and Takano, Hideki},
	month = jan,
	year = {1999}
}

@article{andrews_effect_2017,
	title = {Effect of {Concentration}, {Temperature}, and {Interelectrode} {Gap} on the {Voltage} {Drop} in an {Electrochemical} {System} of {GdCl}3-{LiCl}-{KCl}},
	volume = {116},
	url = {http://ansannual.org/wp-content/data/polopoly_fs/1.3584770.1494347339!/fileserver/file/768394/filename/062.pdf},
	urldate = {2018-03-26},
	journal = {Transactions of the American Nuclear Society},
	author = {Andrews, Hunter and Phongikaroon, Supathorn},
	month = jun,
	year = {2017}
}

@article{park_study_2008,
	title = {Study on a {Salt} {Evaporation} of the {Uranium} {Deposits} from an {Electrorefiner}},
	url = {http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/40/003/40003954.pdf},
	abstract = {Uranium metal is electrodeposited onto a solid cathode during the electrorefining process.
Uranium deposits from an electrorefiner contain about 30{\textasciitilde}40 wt\% salts. In order to recover pure uranium
and transform it into metal ingots, the salts have to be removed. A salt distiller is adapted for a salt
evaporation. A batch operation for the salt removal is carried out by a heating and vacuum evaporation. It
is operated at 700 {\textasciitilde} 1000 oC and less than 1 Torr, respectively. The behaviors of the salt evaporations
were investigated by focusing on the effects of the vacuum pressure and the holding temperature on the salt
distillation. The salt removal efficiencies were obtained with regards to the operational conditions. The
Hertz-Langmuir relation was applied to the experimental results of the salt evaporations. The effective
evaporation coefficients of the relation were obtained with regards to the operational conditions. The lower
the vacuum pressure and the higher the holding temperature were, the higher the removal efficiencies of
the salts were.},
	urldate = {2018-04-27},
	journal = {ATALANTE},
	author = {Park, Sung Bin and Cho, Dong Wook and Oh, Gyu Hwan and Lee, Jong Hyeon and Hwang, Sung Chan and Kang, Young Ho and Lee, Han Soo and Kim, Eung Ho and Park, Seong Won},
	month = may,
	year = {2008}
}

@article{lee_advanced_2008,
	title = {Advanced {Electrorefining} {Process} at {KAERI}},
	url = {http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/40/032/40032685.pdf},
	abstract = {In order to enhance the throughput of a pyroprocessing in which electrochemical processes are
mostly engaged, the design of a continuous concept is required. The graphite cathode in the electrorefiner
enables the uranium deposit on the cathodes to be stripped off spontaneously, resulting in a continuous
reaction. The collected uranium deposits at the bottom of the inner cone of the reactor are transferred by a
conveyer. The residuals in the anode basket after the uranium is depleted are noble metals. These are also
collected at the bottom of the outer shell of the reactor, and conveyed from the reactor for a further
treatment. This work addresses the design of the electrorefiner for a continuous operation. The behavior
of particles such as uranium dendrites or noble metals was analyzed to achieve the proper operating
conditions. The operating conditions for the cathode processor in which molten salt is distilled were also
investigated.},
	urldate = {2018-03-09},
	journal = {ATALANTE 2008},
	author = {Lee, Hansoo and Lee, Jong Hyun and Park, Sung Bin and Lee, Yoon Sang and Kim, Eung Ho and Park, Sung Won},
	month = may,
	year = {2008}
}

@article{lee_assessment_2009,
	title = {Assessment of a {High}-{Throughput} {Electrorefining} {Concept} for a {Spent} {Metallic} {Nuclear} {Fuel}—{II}: {Electrohydrodynamic} {Analysis} and {Validation}},
	volume = {165},
	issn = {0029-5450, 1943-7471},
	shorttitle = {Assessment of a {High}-{Throughput} {Electrorefining} {Concept} for a {Spent} {Metallic} {Nuclear} {Fuel}—{II}},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT09-A4108},
	doi = {10.13182/NT09-A4108},
	language = {en},
	number = {3},
	urldate = {2018-07-17},
	journal = {Nuclear Technology},
	author = {Lee, J. H. and Oh, K. H. and Kang, Y. H. and Hwang, S. C. and Lee, H. S. and Shim, J. B. and Kim, E. H. and Park, S. W.},
	month = mar,
	year = {2009},
	pages = {370--379}
}

@article{li_anodic_nodate,
	title = {{ANODIC} {PROCESS} {OF} {ELECTROREFINING} {SPENT} {NUCLEAR} {FUEL} {IN} {MOLTEN} {LICl}-{KCl}-{UCl}3/{CD} {SYSTEM}},
	abstract = {This article summarizes the experimental results and engineering aspects regarding the anodic process for electrorefining 100 irradiated driver fuel assemblies, a demonstration project for the Department of Energy (DOE) to treat spent nucle ar fuel. The focus is on the anode due to its unique geometry (fuel dissolution baskets loaded with chopped irradiated fuel segments), complex chemical compositions, highly demanding process goals and their significance to the entire spent fuel treatment process. Chemical analysis results of cladding hull samples were used as the key criteria to evaluate the effectiveness of the uranium dissolution and noble metal retention. Parametric study indicated that the diffusion of reactants in the porous fuel matrix was the rate-controlling step to the uranium dissolution from the chopped fuel segments. Anode resistance was the most effective parameter to assess the completeness of uranium dissolution and noble metal retention.},
	language = {en},
	author = {Li, S X},
	pages = {13}
}

@article{korenko_electrochemical_2013,
	title = {Electrochemical separation of uranium in the molten system {LiF}–{NaF}–{KF}–{UF}4},
	volume = {440},
	issn = {00223115},
	url = {http://linkinghub.elsevier.com/retrieve/pii/S002231151300696X},
	doi = {10.1016/j.jnucmat.2013.04.078},
	abstract = {This article is focused on the electrochemical investigation (cyclic voltammetry and related studies) of possible reduction of U4+ ions to metal uranium in the molten system LiF–NaF–KF(eut.)–UF4 that can provide basis for the electrochemical extraction of uranium from molten salts. Two-step reduction mechanism for U4+ ions involving one electron exchange in soluble/soluble U4+/U3+ system and three electrons exchange in the second step were found on the nickel working electrode. Both steps were found to be reversible and diffusion controlled. Based on cyclic voltammetry, the diffusion coefﬁcients of uranium ions at 530 °C were found to be D(U4+) = 1.64 Â 10À5 cm2 sÀ1 and D(U3+) 1.76 Â 10À5 cm2 sÀ1. Usage of the nickel spiral electrode for electroreﬁning of uranium showed fairly good feasibility of its extraction. However some oxidant present during the process of electroreﬁning caused that the solid deposits contained different uranium species such as UF3, UO2 and K3UO2F5.},
	language = {en},
	number = {1-3},
	urldate = {2018-07-16},
	journal = {Journal of Nuclear Materials},
	author = {Korenko, M. and Straka, M. and Szatmáry, L. and Ambrová, M. and Uhlíř, J.},
	month = sep,
	year = {2013},
	pages = {332--337}
}

@article{noauthor_non-destructive_nodate,
	title = {Non-{Destructive} {Assay}: {Instruments} and {Techniques} for {Agency} {Safeguards}},
	volume = {19},
	url = {https://www.iaea.org/sites/default/files/publications/magazines/bulletin/bull19-5/19503403437.pdf},
	number = {5},
	urldate = {2018-07-10},
	journal = {IAEA Bulletin},
	pages = {34--37}
}

@techreport{maggos_update_2015,
	title = {Update on {Electrochemical} {Mass} {Balance} {Modeling} for {Safeguards}},
	abstract = {Pyrochemical recycling of used nuclear has recently been an area of focus for the Material Protection, Accounting, and Control Technologies (MPACT) Campaign as this technology becomes more advanced. Therefore, chemical process models that simulate the operations within an electrochemical used fuel treatment facility are being developed to support the design and implementation of electrochemical process monitoring and material accountability systems. These codes predict the evolving material distribution of uranium and transuranics (TRU), as well as significant fission products and process components, in an electrochemical facility and in the electrorefiner in particular. Calculation of the in-process inventory serves as part of an integrated approach to safeguards by informing the design and selection of measurement techniques, sensor arrangement and measurement frequency, and the development of specialized analysis tools. The ability to predict material inventory may also be necessary when direct measurement is not practical during process operations, or when a fully integrated set of processes is not available.},
	language = {en},
	number = {ANL/FCRD-MPACT/2015-9-2},
	author = {Maggos, Laura E and Pereira, Candido and Caputo, John A F and Copple, Jacqueline M},
	month = sep,
	year = {2015},
	pages = {13},
	file = {Maggos et al. - 2015 - Update on Electrochemical Mass Balance Modeling fo.pdf:C\:\\Users\\Greg\\Zotero\\storage\\UX9JP9RV\\Maggos et al. - 2015 - Update on Electrochemical Mass Balance Modeling fo.pdf:application/pdf}
}

@article{niedrach_uranium_1956,
	title = {Uranium {Purification} by {Electrorefining}},
	volume = {103},
	issn = {00134651},
	url = {http://jes.ecsdl.org/cgi/doi/10.1149/1.2430398},
	doi = {10.1149/1.2430398},
	abstract = {The feasibility of a high temperature electrorefining process for decontamination of U from associated fission products was demonstrated. Low-melting alloys of U with Ni were used to obtain molten products at temperatures below the melting point of pure U. Effects of temperature, current, and salt-bath composition on cell efficiency and cell operation are discussed.},
	language = {en},
	number = {9},
	urldate = {2018-07-10},
	journal = {Journal of The Electrochemical Society},
	author = {Niedrach, Leonard W. and Glamm, Arthur C.},
	year = {1956},
	pages = {521}
}

@article{saleh_electrowinning_1997,
	title = {Electrowinning of {Nonnoble} {Metals} with {Simultaneous} {Hydrogen} {Evolution} at {Flow}‐{Through} {Porous} {Electrodes} {III}. {Time} {Effects}},
	volume = {144},
	issn = {0013-4651, 1945-7111},
	url = {http://jes.ecsdl.org/content/144/3/922},
	doi = {10.1149/1.1837508},
	language = {en},
	number = {3},
	urldate = {2018-07-27},
	journal = {Journal of The Electrochemical Society},
	author = {Saleh, Mahmoud M. and Weidner, John W. and El‐Anadouli, Bahgat E. and Ateya, Badr G.},
	month = mar,
	year = {1997},
	pages = {922--927}
}

@techreport{noauthor_spent_2011,
	type = {State-of-the-art},
	title = {Spent {Nuclear} {Fuel} {Assay} {Data} for {Isotopic} {Validation}},
	url = {https://www.oecd-nea.org/science/wpncs/ADSNF/SOAR_final.pdf},
	urldate = {2018-04-17},
	institution = {OECD, Nuclear Energy Agency},
	month = jun,
	year = {2011}
}

@techreport{cipiti_modeling_2012,
	title = {Modeling and design of integrated safeguards and security for an electrochemical reprocessing facility.},
	url = {https://www.osti.gov/biblio/1055891-modeling-design-integrated-safeguards-security-electrochemical-reprocessing-facility},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {English},
	number = {SAND2012-9303},
	urldate = {2019-05-02},
	institution = {Sandia National Laboratories},
	author = {Cipiti, Benjamin B. and Duran, Felicia Angelica and Key, Bradley Robert and Liu, Yaxi and Lozano, Ivan and Ward, Rebecca},
	month = oct,
	year = {2012},
	doi = {10.2172/1055891}
}

@techreport{michael_f._simpson_developments_2012,
	title = {Developments of {Spent} {Nuclear} {Fuel} {Pyroprocessing} {Technology} at {Idaho} {National} {Laboratory}},
	url = {http://www.osti.gov/servlets/purl/1044209/},
	language = {en},
	number = {INL/EXT-12-25124, 1044209},
	urldate = {2018-07-10},
	author = {{Michael F. Simpson}},
	month = mar,
	year = {2012},
	doi = {10.2172/1044209}
}

@article{lee_modeling_2016,
	title = {Modeling of oxide reduction in repeated-batch pyroprocessing},
	volume = {88},
	issn = {03064549},
	url = {http://linkinghub.elsevier.com/retrieve/pii/S0306454915005174},
	doi = {10.1016/j.anucene.2015.10.031},
	abstract = {Pyroprocessing is a complicated batch-type operation, involving a highly complex material flow logic with a huge number of unit processes. Discrete event system modeling was used to create an integrated operation model for which simulation showed that dynamic material flow could be accomplished to provide considerable insight into the process operation. In the model simulation, the amount of material transported upstream and downstream in the process satisfies a mass balance equation while considering the hold-up incurred by every batch operation. This study also simulated, in detail, an oxide reduction group process embracing electrolytic reduction, cathode processing, and salt purification. Based on the default operation scenario, it showed that complex material flows could be precisely simulated in terms of the mass balance. Specifically, the amount of high-heat elements remaining in the molten salt bath is analyzed to evaluate the operation scenario.},
	language = {en},
	journal = {Annals of Nuclear Energy},
	author = {Lee, Hyo and Suk Im, Hun and Il Park, Geun},
	month = feb,
	year = {2016},
	pages = {1--11},
	file = {Lee et al. - 2016 - Modeling of oxide reduction in repeated-batch pyro.pdf:/home/gtw2/Zotero/storage/CNLLDCTC/Lee et al. - 2016 - Modeling of oxide reduction in repeated-batch pyro.pdf:application/pdf}
}

@article{huff_fundamental_2016,
	title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework},
	volume = {94},
	issn = {0965-9978},
	url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229},
	doi = {10.1016/j.advengsoft.2016.01.014},
	abstract = {As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.},
	urldate = {2016-02-12},
	journal = {Advances in Engineering Software},
	author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.},
	month = apr,
	year = {2016},
	keywords = {agent based modeling, and Science, Computer Science - Computational Engineering, Computer Science - Computational Engineering, Finance, and Science, Computer Science - Mathematical Software, Computer Science - Multiagent Systems, Computer Science - Software Engineering, D.2.13, D.2.4, Finance, I.6.7, I.6.8, Nuclear Engineering, Nuclear fuel cycle, Nuclear Fuel Cycle, Object orientation, Simulation, Systems analysis, Systems Analysis},
	pages = {46--59},
	annote = {Arfc {\textgreater} Cyclus},
	annote = {arXiv: 1509.03604},
	file = {arXiv\:1509.03604 PDF:/Users/gwenchee/Zotero/storage/3IFS96MV/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/gwenchee/Zotero/storage/A9P4584A/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv.org Snapshot:/Users/gwenchee/Zotero/storage/KXHGGIDF/1509.html:text/html;arXiv.org Snapshot:/Users/gwenchee/Zotero/storage/MKRH5AKM/1509.html:text/html;fundamentals.pdf:/Users/gwenchee/Zotero/storage/BJ5VI3CR/fundamentals.pdf:application/pdf;fundamentals.pdf:/Users/gwenchee/Zotero/storage/JIE6VPKS/fundamentals.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/gwenchee/Zotero/storage/R9WQU82P/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/Users/gwenchee/Zotero/storage/7S2VTED7/S0965997816300229.html:text/html;ScienceDirect Snapshot:/Users/gwenchee/Zotero/storage/G9M2I8J2/login.html:text/html;ScienceDirect Snapshot:/Users/gwenchee/Zotero/storage/2VKV9XTG/S0965997816300229.html:text/html}
}

@article{Yilmaz_2016,
	title = {Online Diversion Detection in Nuclear Fuel Cycles via Multimodal Observations},
	author = {Yilmaz, Y. and Hou, E. and Hero, A. O.},
	year = {2016},
	annote = {arXiv:1605.00282}
}

@article{carlsen_cycamore_2014,
	title = {Cycamore v1.0.0},
	author = {Carlsen, R W and Gidden, M and Huff, K D and Opotowsky, A C and Rakhimov, O and Scopatz, A M and Wilson, P},
	year = {2014},
	month = jun,
}

@article{Hou_2016,
	title = {Diversion Detection in Partially Observed Nuclear Fuel Cycle Networks},
	author = {Hou, E. and Yilmaz, Y. and Hero, A. O.},
	year = {2016},
	annote = {arXiv:1604.04322}
}

@article{flowsheet_1998,
	title = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	shorttitle = {Spent {Nuclear} {Fuel} {Reprocessing} {Flowsheet}},
	url = {https://www.oecd-nea.org/science/docs/2012/nsc-wpfc-doc2012-15.pdf},
	language = {en},
	urldate = {2018-03-14},
	journal = {Nuclear Energy Agency},
	author = {{Organisation for Economic Co-operation and Development}},
	month = jun,
	year = {2012},
	file = {Organisation for Economic Cooperation and Development - 1998 - Organisation for economic cooperation and developm.pdf:C\:\\Users\\Greg\\Zotero\\storage\\LTWXQPK6\\Organisation for Economic Cooperation and Development - 1998 - Organisation for economic cooperation and developm.pdf:application/pdf}
}

@techreport{frigo_conceptual_2003,
	title = {A conceptual advanced pyroprocess recycle facility.},
	url = {https://www.osti.gov/biblio/981298},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {ENGLISH},
	number = {ANL/CMT/CP-111325},
	urldate = {2019-10-10},
	institution = {Proc., American Nuclear Society : La Grange, IL, pp. 981-985},
	author = {Frigo, A. A. and Wahlquist, D. R. and Willit, J. L.},
	month = jan,
	year = {2003},
	file = {Snapshot:/home/gtw2/Zotero/storage/M4RD8D3E/981298.html:text/html}
}

@book{international_atomic_energy_agency_implications_2004,
	address = {Vienna},
	series = {Technical report series},
	title = {Implications of partitioning and transmutation in radioactive waste management},
	isbn = {978-92-0-115104-9},
	abstract = {Partitioning and transmutation (P\&T) is a potential complementary route in the management of spent fuel resulting from the generation of nuclear power. It has the potential to open new avenues for long term waste management by eliminating long term radionuclides and their thermal effects and thus reducing the necessity or capacities of disposal facilities. Recycling and reuse of nuclear material and other transuranic radioisotopes would have positive effects on the sustainability of nuclear energy and reduce proliferation concerns by burning nuclear material and other transuranic radionuclides. This report analyzes, from an international perspective, the current status of P\&T, the potential options for its implementation and its impact on waste management programs and strategies},
	language = {en},
	number = {no. 435},
	publisher = {International Atomic Energy Agency},
	editor = {International Atomic Energy Agency},
	year = {2004},
	note = {OCLC: ocm59136942},
	keywords = {Management, Hazardous wastes, Radioactive wastes, Transmutation (Chemistry)},
	file = {International Atomic Energy Agency - 2004 - Implications of partitioning and transmutation in .pdf:/home/gtw2/Zotero/storage/MHS986QX/International Atomic Energy Agency - 2004 - Implications of partitioning and transmutation in .pdf:application/pdf}
}

@article{wigeland_nuclear_2014,
	title = {Nuclear {Fuel} {Cycle} {Evaluation} and {Screening} - {Final} {Report}},
	url = {https://fuelcycleevaluation.inl.gov/Shared%20Documents/ES%20Main%20Report.pdf},
	language = {en},
	urldate = {2017-03-29},
	journal = {US Department of Energy},
	author = {Wigeland, R and Taiwo, T and Ludewig, H and Todosow, M and Halsey, W and Gehin, J and Jubin, R and Buelt, J and Stockinger, S and Jenni, K and Oakley, B},
	year = {2014},
	pages = {51},
	file = {ES Main Report.pdf:/home/gtw2/Zotero/storage/WEVPB9EQ/ES Main Report.pdf:application/pdf;Wigeland et al. - 2014 - Nuclear Fuel Cycle Evaluation and Screening – Fina.pdf:/home/gtw2/Zotero/storage/HDRFTE88/Wigeland et al. - 2014 - Nuclear Fuel Cycle Evaluation and Screening – Fina.pdf:application/pdf}
}

@article{li_electrorefining_2005,
	title = {Electrorefining {Experience} for {Pyrochemical} {Processing} of {Spent} {EBR}-{II} {Driver} {Fuel}},
	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.},
	language = {en},
	number = {487},
	author = {Li, Shelly X and Johnson, Thomas A and Westphal, Brian R and Goff, Kenneth M and Benedict, Robert W},
	year = {2005},
	pages = {7},
	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}
}

@article{lee_determination_2012,
	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}},
	volume = {179},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT11-77},
	doi = {10.13182/NT11-77},
	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\%.},
	number = {2},
	urldate = {2019-10-23},
	journal = {Nuclear Technology},
	author = {Lee, Tae-Hoon and Kim, Young-Soo and Kwon, Tae-Je and Shin, Hee-Sung and Kim, Ho-Dong},
	month = aug,
	year = {2012},
	pages = {196--204},
	file = {Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\L2RUBHAM\\NT11-77.html:text/html}
}

@book{basseville_detection_1993,
	series = {Prentice {Hall} information and system sciences series},
	title = {Detection of {Abrupt} {Changes}: {Theory} and {Application}},
	isbn = {0-13-126780-9},
	url = {ftp://ftp.irisa.fr/local/as/mb/k11.pdf},
	language = {English},
	urldate = {2018-11-09},
	publisher = {Prentice Hall},
	author = {Basseville, Michele and Nikiforov, Igor V.},
	month = apr,
	year = {1993},
	file = {Basseville.pdf:C\:\\Users\\Greg\\Zotero\\storage\\7Q9JS3DM\\Basseville.pdf:application/pdf}
}

@article{hayyan_investigating_2013,
	title = {Investigating the electrochemical windows of ionic liquids},
	volume = {19},
	issn = {1226-086X},
	url = {http://www.sciencedirect.com/science/article/pii/S1226086X12002353},
	doi = {10.1016/j.jiec.2012.07.011},
	abstract = {The structure effect on the electrochemical windows ({EWs}) was studied using cyclic voltammetry ({CV}) in 16 ionic liquids ({ILs}), consisting of various cations such as piperidinium, pyridinium, pyrrolidinium, phosphonium, morpholinium, ammonium, sulfonium and imidazolium, and anions including bis(trifluoromethylsulfonyl)imide, tris(pentafluoroethyl)trifluorophosphate, dicyanamide, trifluoroacetate and trifluoromethanesulfonate. It was found that all studied {ILs} have good {EWs} to be utilized as electrolytes in different electrochemical applications pertaining to industry. Furthermore, it was found that the structure of {ILs} affected the {EW} and both the cation and anion have important effect on the reductive and oxidative limits, respectively. The reductive limits of the studied {ILs} were found to follow the sequence of [P14,666]+{\textgreater}[N112,1O2]+{\textgreater}[{HMPyrr}]+{\textgreater}[{BMPyrr}]+{\textgreater}[{EMIm}]+{\textgreater}[{MOEMMor}]+?[{MOPMPip}]+{\textgreater}[S222]+{\textgreater}[{BMPy}]+?[{HPy}]+?[{HPPy}]+. The oxidative limits were found to follow the sequence of [{TFSI}]?{\textgreater}[{TPTP}]?{\textgreater}[{TfO}]?{\textgreater}[{DCA}]?{\textgreater}[{TFA}]?.},
	pages = {106--112},
	number = {1},
	journaltitle = {Journal of Industrial and Engineering Chemistry},
	shortjournal = {Journal of Industrial and Engineering Chemistry},
	author = {Hayyan, Maan and Mjalli, Farouq S. and Hashim, Mohd Ali and {AlNashef}, Inas M. and Mei, Tan Xue},
	urldate = {2019-12-01},
	month = jan,
	year = {2013}.
	langid = {english},
	keywords = {Ag/{AgCl} electrode, Cut-off current, Cyclic voltammetry, Electrochemical window, Glassy carbon macro-electrode, Ionic liquid},
	file = {ScienceDirect Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\4ZDVEX9A\\S1226086X12002353.html:text/html}
}

@phdthesis{gidden_agent-based_2015,
	location = {Madison, {WI}, United States},
	title = {An Agent-Based Modeling Framework and Application for the Generic Nuclear Fuel Cycle},
	abstract = {Key components of a novel methodology and implementation of an agent-based, dynamic nuclear fuel cycle simulator, Cyclus , are presented. The nuclear fuel cycle is a complex, physics-dependent supply chain. To date, existing dynamic simulators have not treated constrained fuel supply, time-dependent, isotopic-quality based demand, or fuel fungibility particularly well. Utilizing an agent-based methodology that incorporates sophisticated graph theory and operations research techniques can overcome these deficiencies. This work describes a simulation kernel and agents that interact with it, highlighting the Dynamic Resource Exchange ({DRE}), the supply-demand framework at the heart of the kernel. The key agent-{DRE} interaction mechanisms are described, which enable complex entity interaction through the use of physics and socio-economic models. The translation of an exchange instance to a variant of the Multicommodity Transportation Problem, which can be solved feasibly or optimally, follows. An extensive investigation of solution performance and fidelity is then presented. Finally, recommendations for future users of Cyclus and the {DRE} are provided.},
	school = {University of Wisconsin},
	type = {phdthesis},
	author = {Gidden, Matthew J.},
	month = mar,
	year = {2015},
	file = {gidden_agent-based_2015.pdf:C\:\\Users\\Greg\\Zotero\\storage\\E6J9VKJM\\gidden_agent-based_2015.pdf:application/pdf;Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\62GAD8YI\\1.html:text/html}
}

@inproceedings{skutnik_cyborg:_2016,
	address = {Las Vegas, Nevada, United States},
	series = {Fuel {Cycle} and {Waste} {Management}: {General}{\textemdash}{II}},
	title = {{CyBORG}: {An} {ORIGEN}-{Based} {Reactor} {Analysis} {Capability} for {Cyclus}},
	volume = {115},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Skutnik, Steven E. and Sly, Nicholas C. and Littell, Jennifer Lynn},
	month = nov,
	year = {2016},
	keywords = {C++, Code, Fuel cycle, Geniusv2, Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS), Simulation, Technology},
	pages = {299--301}
}

@techreport{schneider_integrated_2016,
	title = {An {Integrated} {Fuel} {Depletion} {Calculator} for {Fuel} {Cycle} {Options} {Analysis}},
	url = {http://www.osti.gov/servlets/purl/1258475/},
	language = {en},
	number = {12-4065, 1258475},
	urldate = {2019-12-03},
	author = {Schneider, Erich and Scopatz, Anthony},
	month = apr,
	year = {2016},
	doi = {10.2172/1258475},
	pages = {12--4065, 1258475},
	file = {Schneider and Scopatz - 2016 - An Integrated Fuel Depletion Calculator for Fuel C.pdf:C\:\\Users\\Greg\\Zotero\\storage\\T8ZXE4A9\\Schneider and Scopatz - 2016 - An Integrated Fuel Depletion Calculator for Fuel C.pdf:application/pdf}
}

@misc{mcgarry_mbmore_2017,
	title = {mbmore v0.1},
	shorttitle = {mbmore version 0.1},
	url = {https://figshare.com/articles/mbmore/5097694},
	abstract = {Collection of custom Cyclus facility archetypes dedicated to modeling nonproliferation issues as part of the Consortium of Verification technology.Features include non-deterministic behavior models.},
	publisher = {GitHub},
	author = {McGarry, Meghan and Mouginot, Baptiste},
	month = jun,
	year = {2017},
	doi = {10.6084/m9.figshare.5097694.v1},
	keywords = {Consortium of Verification Technology, CVT, cyclus, Fuel Cycle Simulation, Nuclear Fuel Cycle Simulation},
	file = {Figshare Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\QZ6HUER3\\5097694.pdf:application/pdf}
}

@inproceedings{mummah_material_2019,
	address = {Champaign, IL},
	title = {Material {Diversion} {Analysis} {Within} a {Fuel} {Cycle} {Simulator}},
	abstract = {The IAEA considers a State{\textquoteright}s entire fuel cycle capability when evaluating and implementing safeguards, a process known as the State-Level Approach. Conducting Acquisition Path Analysis (APA) is one aspect of ensuring efficient use of safeguards resources and an objective evaluation of member States. APA is designed to identify, characterize, and rank technically-feasible pathways through a fuel cycle to produce weapons-usable material. The focus of previous APA tools has been identifying diversion pathways. However, the ability to analyze pathways for material throughput capacity is crucial in estimating pathway completion times and implementing tailored safeguards. Fuel cycle simulators can be used to generate and study acquisition pathways with more detail by tracking material flows. The Cyclus fuel cycle simulator inherently represents the flows of material among facilities as a graph that can be traversed to identify the numerous acquisition pathways. This work adds material balance areas to Cyclus facilities such that a richer set of acquisition path steps can be studied. Cyclus facility archetypes implement material buffers for holding material objects internally, but flows between these buffers are internal to the archetype. A mechanism is introduced to expose the flows between these internal buffers in a way that extends the full system flow graph. A simplified case will be used to generate all possible diversion pathways and their material throughput capacity. A similar fuel cycle with a single clandestine facility will also be simulated to demonstrate how the presence of a clandestine facility expands the acquisition paths available to a diverting State.},
	author = {Mummah, Kathryn A.},
	month = jun,
	year = {2019},
	publisher = {Technical Workshop on Fuel Cycle Simulation}
}

@inproceedings{root_see_2019,
	address = {LANL},
	title = {{SEE} {LANL} - {Nuclear} {Safeguards} {Training}},
	abstract = {There is a brief review of basic neutron interactions, nondestructive assay measurements,
and any other concepts of interest to the students attending the course.
The course is organized into a series of lessons and exercises to help students understand
various nondestructive assay concepts that are used in nuclear safeguards. Each lesson
consists of a combination of lectures and laboratory exercises. For the laboratory
exercises, the students are divided into small teams to encourage active participation of
every student in the learning process in an enjoyable way},
	author = {Root, Margaret and Miller, James},
	month = jan,
	year = {2019}
}

@book{duderstadt_nuclear_1976,
	address = {New York},
	edition = {1 edition},
	title = {Nuclear {Reactor} {Analysis}},
	isbn = {978-0-471-22363-4},
	abstract = {Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.},
	language = {English},
	publisher = {Wiley},
	author = {Duderstadt, James J. and Hamilton, Louis J.},
	month = jan,
	year = {1976}
}

@article{ahluwalia_uranium_2004,
	title = {Uranium {Transport} in a {High}-{Throughput} {Electrorefiner} for {EBR}-{II} {Blanket} {Fuel}},
	volume = {145},
	issn = {0029-5450, 1943-7471},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT04-A3461},
	doi = {10.13182/NT04-A3461},
	language = {en},
	number = {1},
	urldate = {2019-05-02},
	journal = {Nuclear Technology},
	author = {Ahluwalia, Rajesh K. and Hua, Thanh Q. and Vaden, DeeEarl},
	month = jan,
	year = {2004},
	pages = {67--81},
	file = {Ahluwalia et al. - 2004 - Uranium Transport in a High-Throughput Electrorefi.pdf:C\:\\Users\\Greg\\Zotero\\storage\\GNSTVMIE\\Ahluwalia et al. - 2004 - Uranium Transport in a High-Throughput Electrorefi.pdf:application/pdf}
}

@inproceedings{yacout_vision_2006,
	title = {{VISION} -- {Verifiable} {Fuel} {Cycle} {Simulation} of {Nuclear} {Fuel} {Cycle} {Dynamics}},
	url = {http://www.inl.gov/technicalpublications/Documents/3394908.pdf},
	booktitle = {Waste {Management} {Symposium}},
	author = {Yacout, A. M. and Jacobson, J. J. and Matthern, G. E. and Piet, S. J. and Shropshire, D. E. and Laws, C.},
	year = {2006},
	file = {Google Scholar Linked Page:C\:\\Users\\Greg\\Zotero\\storage\\P3TPNT3H\\Yacout et al. - 2006 - VISION{\textendash}Verifiable Fuel Cycle Simulation of Nuclear.pdf:application/pdf}
}

@techreport{bell_origen_1973,
	title = {{ORIGEN} - {The} {ORNL} {Isotope} {Generation} and {Depletion} {Code}},
	shorttitle = {{ORIGEN}},
	abstract = {ORIGEN is a versatile point depletion code which solves the equations of radioactive growth and decay for large numbers of isotopes with arbitrary coupling.  The code uses the matrix exponential method to solve a large system of coupled, linear, first-order ordinary differential equations with constant coefficients.  The general nature of the matrix exponential method permits the treatment of complex decay and transmutation schemes.  An extensive library of nuclear data has been compiled, including half-lives and decay schemes, neutron absorbtion, cross sections, fission yields, disintegration energies, and multigroup photon release data.  ORIGEN has been used to compute the compositions and radiactivity of fission products, cladding materials, and fuel materials in LWRs, LMFBRs, MSBRs, and HTGRs.  The applications are illustrated with calculated inventories and radiation levels for spent fuel irradiated to a burnup of 33,000 MWd/metric ton in a PWR spectrum.},
	number = {ORNL-4628},
	institution = {Oak Ridge National Laboratory},
	author = {Bell, M.},
	month = may,
	year = {1973},
	note = {Software, Codes \& Tools},
	keywords = {Cladding, Code, Coupling, Decay, Fission, Growth, Neutron, ORIGEN, Radiation, Radioactivity, Transmutation, Versatile Point Depletion Code},
	file = {Bell 1973 ORIGEN.pdf:C\:\\Users\\Greg\\Zotero\\storage\\FUJ5IKU7\\Bell 1973 ORIGEN.pdf:application/pdf}
}

@article{zimmerman_orion_2007,
	title = {The orion fuel cycle modelling code},
	url = {http://inis.iaea.org/Search/search.aspx?orig_q=RN:39088799},
	language = {English},
	urldate = {2018-09-06},
	journal = {Actinide and fission product partitioning and transmutation},
	author = {Zimmerman, C. H. and Moore, R. G. and Robbins, C.},
	year = {2007},
	file = {Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\UZMDQ5RI\\search.html:text/html}
}

@article{coquelet-pascal_cosi6:_2015,
	title = {{COSI}6: {A} {Tool} for {Nuclear} {Transition} {Scenario} {Studies} and {Application} to {SFR} {Deployment} {Scenarios} with {Minor} {Actinide} {Transmutation}},
	volume = {192},
	issn = {0029-5450, 1943-7471},
	shorttitle = {{COSI}6},
	url = {https://www.tandfonline.com/doi/full/10.13182/NT15-20},
	doi = {10.13182/NT15-20},
	language = {en},
	number = {2},
	urldate = {2019-07-07},
	journal = {Nuclear Technology},
	author = {Coquelet-Pascal, C. and Tiphine, M. and Krivtchik, G. and Freynet, D. and Cany, C. and Eschbach, R. and Chabert, C.},
	month = nov,
	year = {2015},
	pages = {91--110},
	file = {Coquelet-Pascal et al. - 2015 - COSI6 A Tool for Nuclear Transition Scenario Stud.pdf:C\:\\Users\\Greg\\Zotero\\storage\\64YP6ZEL\\Coquelet-Pascal et al. - 2015 - COSI6 A Tool for Nuclear Transition Scenario Stud.pdf:application/pdf;Snapshot:C\:\\Users\\Greg\\Zotero\\storage\\6ICA6XUV\\a_37671.html:text/html}
}

gha_language: TeX


text:
package model

// SubscriptionInfo model
type SubscriptionInfo struct {
	CallbackURL          string `json:"callbackUrl,omitempty"`
	DestinationDeviceID  string `json:"ddid,omitempty"`
	Description          string `json:"description,omitempty"`
	MessageType          string `json:"messageType,omitempty"`
	Name                 string `json:"name,omitempty"`
	SourceDeviceID       string `json:"sdid,omitempty"`
	SourceDeviceTypeID   string `json:"sdtid,omitempty"`
	UserID               string `json:"uid,omitempty"`
	SubscriptionType     string `json:"subscriptionType,omitempty"`
	AWSKey               string `json:"awsKey,omitempty"`
	AWSSecret            string `json:"awsSecret,omitempty"`
	AWSRegion            string `json:"awsRegion,omitempty"`
	AWSKinesisStreamName string `json:"awsKinesisStreamName,omitempty"`
	IncludeSharedDevices bool   `json:"includeSharedDevices,omitempty"`
}

license: MIT

license_type: permissive

branch_name: refs/heads/master

extension: go


text:
package utils

import (
	"errors"
	"fmt"
	"strings"
	"time"

	ldap "gopkg.in/ldap.v2"
)

type LdapConf struct {
	Addr       string   `yaml:"addr"`
	BaseDn     string   `yaml:"base_dn"`
	Filter     string   `yaml:"filter"`
	Attributes []string `yaml:"attributes,flow"`
	BindDn     string   `yaml:"bind_dn"`
	BindPasswd string   `yaml:"bind_passwd"`
}

type LdapResult struct {
	DN         string
	Attributes map[string][]string
}

type Ldap struct {
	conf *LdapConf `inject:""`
}

func (l *Ldap) SetLdapConf(conf *LdapConf) error {
	if err := VerifyLdapConfig(conf); err != nil {
		return err
	}
	l.conf = conf
	return nil
}

func VerifyLdapConfig(conf *LdapConf) (err error) {
	if len(conf.Addr) == 0 || !strings.Contains(conf.Addr, ":") {
		return errors.New("field [ ldap.addr ] missing or wrong format, expect x.x.x.x:389")
	}

	if len(conf.BaseDn) == 0 || !strings.Contains(conf.BaseDn, "DC=") {
		return errors.New("field [ ldap.base_dn ] missing or wrong format, expect OU=xxx,DC=example,DC=com")
	}

	if len(conf.Filter) == 0 {
		return errors.New("field [ ldap.filter ] missing or wrong format")
	}

	if len(conf.Attributes) == 0 {
		return errors.New("field [ ldap.attributes ] missing or wrong format, attributes must be an array")
	}

	if len(conf.BindDn) == 0 || !strings.Contains(conf.BindDn, "DC=") {
		return errors.New("field [ ldap.bind_dn ] missing or wrong format, expect OU=xxx,DC=example,DC=com")
	}

	if len(conf.BindPasswd) == 0 {
		return errors.New("field [ ldap.bind_passwd ] missing or wrong format")
	}

	return nil
}

func (m *Ldap) Auth(username string, password string) (info *LdapResult, err error) {
	userInfo := &LdapResult{}

	ldap.DefaultTimeout = 5 * time.Second

	l, err := ldap.Dial("tcp", m.conf.Addr)
	if err != nil {
		return nil, err
	}
	defer l.Close()

	// First bind with a read only user
	err = l.Bind(m.conf.BindDn, m.conf.BindPasswd)
	if err != nil {
		return nil, err
	}

	// Search for the given username
	searchRequest := ldap.NewSearchRequest(
		m.conf.BaseDn,
		ldap.ScopeWholeSubtree, ldap.NeverDerefAliases, 0, 0, false,
		fmt.Sprintf(m.conf.Filter, username),
		m.conf.Attributes,
		nil,
	)

	sr, err := l.Search(searchRequest)
	if err != nil {
		return nil, err
	}

	if len(sr.Entries) != 1 {
		return nil, errors.New("User does not exist or too many entries returned")
	}

	attributes := make(map[string][]string)
	for _, item := range sr.Entries[0].Attributes {
		attributes[item.Name] = item.Values
	}

	userInfo.DN = sr.Entries[0].DN
	userInfo.Attributes = attributes

	// Bind as the user to verify their password
	err = l.Bind(userInfo.DN, password)
	if err != nil {
		return nil, errors.New("wrong password of user " + username)
	}

	// Rebind as the read only user for any further queries
	err = l.Bind(m.conf.BindDn, m.conf.BindPasswd)
	if err != nil {
		return nil, err
	}

	return userInfo, nil
}

func (m *Ldap) ListUsers() (list []LdapResult, err error) {
	userList := make([]LdapResult, 0)

	ldap.DefaultTimeout = 5 * time.Second

	l, err := ldap.Dial("tcp", m.conf.Addr)
	if err != nil {
		return nil, err
	}
	defer l.Close()

	// First bind with a read only user
	err = l.Bind(m.conf.BindDn, m.conf.BindPasswd)
	if err != nil {
		return nil, err
	}

	// Search for the given username
	searchRequest := ldap.NewSearchRequest(
		m.conf.BaseDn,
		ldap.ScopeWholeSubtree, ldap.NeverDerefAliases, 0, 0, false,
		fmt.Sprintf(m.conf.Filter, "*"),
		m.conf.Attributes,
		nil,
	)

	sr, err := l.Search(searchRequest)
	if err != nil {
		return nil, err
	}

	if len(sr.Entries) == 0 {
		return nil, errors.New("User does not exist")
	}

	for _, userEntry := range sr.Entries {
		userInfo := LdapResult{}
		attributes := make(map[string][]string)
		for _, item := range userEntry.Attributes {
			attributes[item.Name] = item.Values
		}

		userInfo.DN = userEntry.DN
		userInfo.Attributes = attributes
		userList = append(userList, userInfo)
	}

	// Rebind as the read only user for any further queries
	err = l.Bind(m.conf.BindDn, m.conf.BindPasswd)
	if err != nil {
		return nil, err
	}

	return userList, nil
}


text:
@misc{covid19intro1,
    title        = "COVID-19 Overview and Infection Prevention and Control Priorities in non-US Healthcare Settings",
    howpublished = "\url{https://www.cdc.gov/coronavirus/2019-ncov/hcp/non-us-settings/overview/index.html#}",
    year         = 2020,
    note         = "Accessed: 2020-09-24"

     }

@misc{covid19intro2,
    title        = "Assessing Risk Factors for Severe COVID-19 Illness",
    howpublished = "\url{https://www.cdc.gov/coronavirus/2019-ncov/covid-data/investigations-discovery/assessing-risk-factors.html}",
    year         = 2020,
    note         = "Accessed: 2020-09-24"

     }

@misc{data,
    title        = "COVID-19 Cases in Toronto",
    author       = "{Toronto Public Health}",
    howpublished = "\url{https://open.toronto.ca/dataset/covid-19-cases-in-toronto/}",
    year         = 2020,
    note         = "Accessed: 2020-09-23"
     }

@misc{HOSPITAL,
    title        = "Risk Factors for COVID-19 Disease Progression",
    organization = "MASSACHUSETTS GENERAL HOSPITAL",
    howpublished = "\url{https://www.massgeneral.org/assets/MGH/pdf/news/coronavirus/risk-factors-for-severe-COVID-19.pdf}",
    year         = 2020,
    note         = "Accessed: 2020-09-24"
     }

extension: bib


text:
DESCRIPTION = "Sofia-SIP is an open-source SIP User-Agent library, compliant with the IETF RFC3261 specification."
HOMEPAGE = "http://sofia-sip.sourceforge.net/"
LICENSE = "LGPL"

SRC_URI = "${SOURCEFORGE_MIRROR}/${PN}/${P}.tar.gz"

inherit autotools pkgconfig

do_stage() {
autotools_stage_all
}

repository: jdegges/gumstix-pip-oe

repo_name: jdegges/gumstix-pip-oe


text:
DESCRIPTION = "CarHUD Config"
LICENSE = "GPLv2"
LIC_FILES_CHKSUM = "file://LICENSE.txt;md5=b234ee4d69f5fce4486a80fdaf4a4263"

PR = "r3"

SRC_URI = "              \
    file://carhud.cfg \
    file://LICENSE.txt \
    "

do_configure() {
    install -m 0555 ${WORKDIR}/LICENSE.txt ${S}/
}

do_install() {
    # CREATE DIRECTORIES, WE NEED etc
    install -d ${D}${sysconfdir}

    # INSTALL THE FILES
    install -m 0555 ${WORKDIR}/carhud.cfg                 ${D}${sysconfdir}/
}

repository: xtacocorex/meta-rpi

repo_name: xtacocorex/meta-rpi

branch_name: refs/heads/jethro

extension: bb


text:
@article{missing_data_diagnostics,
 abstract = {While systematic reviews of substance abuse interventions hold great promise for informing what works for whom and under what conditions, such reviews must contend with missing data. Missing data can limit the accuracy of statistical analyses or the relevance of the evidence base and deciding how to handle missing data depends on why it is missing in the first place. In this tutorial, we examine methods for exploring missingness in a dataset in ways that can help identify the sources and extent of missingness, as well as clarify gaps in evidence. We demonstrate these methods on a meta-analysis of substance abuse interventions for adolescents to highlight areas where the evidence less clear and where statistical adjustments taken by the original authors appear to have been necessary.},
 author = {Jacob M. Schauer and Karina D\`{i}az and Therese D. Pigott},
 journal = {Alcohol and Alcoholism},
 title = {Exploratory analyses for missing data in meta-analyses},
 year = {accepted}
}


text:
SUMMARY = "library to access web services that claim to be "RESTful""
HOMEPAGE = "https://wiki.gnome.org/Projects/Librest"
LICENSE = "LGPLv2.1"
LIC_FILES_CHKSUM = "file://COPYING;md5=2d5025d4aa3495befef8f17206a5b0a1"

GNOMEBASEBUILDCLASS = "autotools"

DEPENDS = " \
    libxml2-native \
    glib-2.0-native \
    glib-2.0 \
    libsoup-2.4 \
"

inherit gnomebase gobject-introspection gtk-doc vala

SRC_URI[archive.md5sum] = "ece4547298a81105f307369d73c21b9d"
SRC_URI[archive.sha256sum] = "0513aad38e5d3cedd4ae3c551634e3be1b9baaa79775e53b2dba9456f15b01c9"

# * gnome environment requires libsoup build with in gnome PACKAGECONFIG
# * libsoup-gnome support was removed upstream three years ago [1]
# [1] https://gitlab.gnome.org/GNOME/librest/commit/8f904a8e2bb38a7bf72245cdf2f1ecad17e9a720
EXTRA_OECONF = "--without-gnome"

do_configure:prepend() {
    # rest expects introspection.m4 at custom location (see aclocal.m4).
    cp -f ${STAGING_DIR_TARGET}/${datadir}/aclocal/introspection.m4 ${S}/build
}

do_compile:prepend() {
    export GIR_EXTRA_LIBS_PATH="${B}/rest/.libs"
}

repository: Intel-BMC/openbmc

repo_name: Intel-BMC/openbmc

gha_license_id: NOASSERTION

gha_language: Python


text:
#    ____  ____
#   /   /\/   /
#  /___/  \  /   Copyright (c) 2021, Xilinx®.
#  \   \   \/    Author: Víctor Mayoral Vilches <victorma@xilinx.com>
#   \   \
#   /   /
#  /___/   /\
#  \   \  /  \
#   \___\/\___\
#
# Vitis HLS macros to integrate High-Level Synthesis (HLS)
# capabilities into the  ROS ament build system
#
# See https://www.xilinx.com/html_docs/xilinx2020_2/vitis_doc/gnq1597858079367.html
# for more on Vitis HLS

#
# Generate a Vitis Tcl script from CMake
#
# .. note:: this macro will command CMake to generate
# the corresponding Tcl script according to the parameters
# designed below. To execute such script use either Vitis CLI
# (e.g. via "vitis_hls -f <tcl-script>") or colcon krs hls.
#
# .. note:: the macro will generate one solution per each clock
# option provided
#
# :param PROJECT: Name of the Vitis HLS project to be created
# :type target: string
#
# :param TOPFUNCTION: Top-level function of the acceleration kernel
# e.g. vadd
# :type target: string
#
# :param SRC: sources for the kernel can be various. Relative paths.
# :type target: string
#
# :param TESTBENCH: source file for the testbench. Relative path.
# :type target: string
#
# :param CLOCK: Clock period in nanoseconds (e.g. 4). One solution will be
# generated per each clock element provided.
# :type target: string
#
# :param HEADERS: one or muliple relative path directories whereto search for
# header files.
# :type target: string
#
# :param SYNTHESIS (optional): Run synthesis
# :type target: bool
#
# :param RTLSIMULATION (optional): Run RTL Simulation
# :type target: bool
#
# :param RTLIMPLEMENTATION (optional): Run RTL implementation
# :type target: bool
#
macro(vitis_hls_generate_tcl)
    set(options SYNTHESIS RTLSIMULATION RTLIMPLEMENTATION)
    set(oneValueArgs PROJECT TOPFUNCTION TESTBENCH)
    set(multiValueArgs SRC HEADERS CLOCK)

    cmake_parse_arguments(VITIS_HLS "${options}" "${oneValueArgs}"
                          "${multiValueArgs}" ${ARGN} )

    # if (CMAKE_SYSTEM_PROCESSOR STREQUAL "aarch64" AND DEFINED CMAKE_SYSROOT})
    if (DEFINED CMAKE_SYSROOT)  # cross compilation, DEFINED CMAKE_SYSROOT

      # set some initial placeholders
      set(VITIS_HLS_PROJECT_VALUE ${VITIS_HLS_PROJECT})
      set(VITIS_HLS_TOPFUNCTION_VALUE ${VITIS_HLS_TOPFUNCTION})

      # define template, with or without include directories
      FILE(WRITE ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
      "open_project -reset @VITIS_HLS_PROJECT_VALUE@\n"
      "add_files @VITIS_HLS_SRC_VALUE@\n"
      )

      if(DEFINED VITIS_HLS_HEADERS)
        # convert to "value1 value2"
        foreach(VITIS_HLS_HEADERS_file ${VITIS_HLS_HEADERS})
          if(IS_ABSOLUTE ${VITIS_HLS_HEADERS_file})
            set(VITIS_HLS_HEADERS_VALUE "${VITIS_HLS_HEADERS_VALUE} -I ${VITIS_HLS_HEADERS_file}")
          else()
            set(VITIS_HLS_HEADERS_VALUE "${VITIS_HLS_HEADERS_VALUE} -I ${CMAKE_SOURCE_DIR}/${VITIS_HLS_HEADERS_file}")
          endif()
        endforeach()

        # NOTE:
        #    See https://gcc.gnu.org/onlinedocs/gcc/Directory-Options.html for the differences
        #     between -isystem and -I
        # FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
        # "add_files -tb @VITIS_HLS_TESTBENCH_VALUE@ -cflags \"-isystem @VITIS_HLS_HEADERS_VALUE@\"\n"
        # )
        FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
        "add_files -tb @VITIS_HLS_TESTBENCH_VALUE@ -cflags \" @VITIS_HLS_HEADERS_VALUE@\"\n")

      else()
        FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
          "add_files -tb @VITIS_HLS_TESTBENCH_VALUE@\n"
        )
      endif()  # VITIS_HLS_HEADERS, add include directories

      FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
      "set_top @VITIS_HLS_TOPFUNCTION_VALUE@\n"
      )

      # determine the SoC at build time and based on the select-ed firmware
      set(FIRMWARE_SOC_PATH ${CMAKE_INSTALL_PREFIX}/../acceleration/firmware/select/SOC)
      file (STRINGS ${FIRMWARE_SOC_PATH} FIRMWARE_SOC)

      foreach(clock_item ${VITIS_HLS_CLOCK})
        FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
        "# solution_${clock_item}ns\n"  # mark each solution with clock ns
        "open_solution -flow_target vitis solution_${clock_item}ns\n"  # mark each solution with clock ns
        "set_part {${FIRMWARE_SOC}}\n"
        "create_clock -period ${clock_item}\n"
        "csim_design -ldflags \"-lOpenCL\" -profile\n"
        )

        if (${VITIS_HLS_SYNTHESIS})
          FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
            "csynth_design\n"
          )
        endif()  # VITIS_HLS_SYNTHESIS

        if (${VITIS_HLS_RTLSIMULATION})
          FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
            "cosim_design -O -rtl verilog -ldflags \"-L/lib/x86_64-linux-gnu\"\n"
          )
        endif()  # VITIS_HLS_RTLSIMULATION

        if (${VITIS_HLS_RTLIMPLEMENTATION})
          FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
            "export_design\n"
          )
        endif()  # VITIS_HLS_RTLIMPLEMENTATION

      # exit at the end
      FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
      "\n"
      )
      endforeach()  # for each clock_item

      # exit at the end
      FILE(APPEND ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in
      "exit\n"
      )

      # set placeholders
      # set(VITIS_HLS_SRC_VALUE ${VITIS_HLS_SRC})  # this gets a list as "value1;value2"
      # we need instead: "value1 value2"
      set(VITIS_HLS_SRC_VALUE "")  # re-initialize, needed if various calls in the same CMakeLists.txt
      foreach(VITIS_HLS_SRC_file ${VITIS_HLS_SRC})
        set(VITIS_HLS_SRC_VALUE "${VITIS_HLS_SRC_VALUE} ${CMAKE_SOURCE_DIR}/${VITIS_HLS_SRC_file}")
      endforeach()
      set(VITIS_HLS_TESTBENCH_VALUE ${CMAKE_SOURCE_DIR}/${VITIS_HLS_TESTBENCH})
      # set(VITIS_HLS_CLOCK_VALUE ${VITIS_HLS_CLOCK})  # not necessary anymore, iterating over clocks above

      # replace placeholders and produce final Tcl script
      configure_file(${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl.in ${CMAKE_BINARY_DIR}/${VITIS_HLS_PROJECT}.tcl)

      # install Tcl script
      ## NOTE: this would move .tcl scripts to the install-* directory. Instead
      ## it's recommended to keep things in build-*, rationale is that install-*
      ## is what we're deploying to the embedded platforms and we want this to be compact
      # install(
      #   FILES
      #     ${CMAKE_BINARY_DIR}/hls.tcl
      #   DESTINATION
      #     lib/${PROJECT_NAME}
      # )
    endif()  # cross compilation, DEFINED CMAKE_SYSROOT
endmacro()  # vitis_acceleration_kernel

branch_name: refs/heads/main

extension: cmake


text:
@article{acharya_mechanosensitive_2018,
 author = {Acharya, Bipul R. and Nestor-Bergmann, Alexander and Liang, Xuan and Gupta, Shafali and Duszyc, Kinga and Gauquelin, Estelle and Gomez, Guillermo A. and Budnar, Srikanth and Marcq, Philippe and Jensen, Oliver E. and Bryant, Zev and Yap, Alpha S.},
 doi = {10.1016/j.devcel.2018.09.016},
 issn = {15345807},
 journal = {Developmental Cell},
 language = {en},
 month = {November},
 number = {4},
 pages = {439--452.e6},
 title = {A mechanosensitive rhoa pathway that protects epithelia against acute tensile stress},
 url = {https://linkinghub.elsevier.com/retrieve/pii/S1534580718307767},
 urldate = {2019-05-30},
 volume = {47},
 year = {2018}
}

gha_license_id: MIT


text:
require ti-dspbios.inc

PV = "5_41_09_34"

SRC_URI[biosbin.md5sum] = "e3e1f334224d8d00e36a238dc71026ea"
SRC_URI[biosbin.sha256sum] = "357c2c01855a1f31f70823bc5afc5d9dc63341270df61d0cf905b172db49f718"

repository: overo/overo-oe-natty

repo_name: overo/overo-oe-natty

branch_name: HEAD


text:
package thermostat

import (
	"encoding/json"
	"fmt"
	"math/rand"
	"sync"

	"github.com/tbarker25/thermostat-api/internal/temp"
)

// nextID stores the next ID to assign to a new thermostat. Note that the ID
// field should be unique.
var nextID uint32 = 1

// Thermostat represents the current state of a thermostat
type Thermostat struct {
	id            uint32
	name          string
	operatingMode OperatingMode
	heatPoint     temp.Temp
	coolPoint     temp.Temp
	fanMode       FanMode
	lock          sync.RWMutex
}

// New thermostat with default values
func New() *Thermostat {
	id := nextID
	nextID++
	return &Thermostat{
		id:            id,
		name:          fmt.Sprintf("thermostat-%d", id),
		operatingMode: ModeOff,
		heatPoint:     temp.Fahrenheit(65),
		coolPoint:     temp.Fahrenheit(80),
		fanMode:       FanAuto,
	}
}

// GetID retrieves a thermostat's unique identifier
func (t *Thermostat) GetID() uint32 {
	return t.id
}

// GetName retrieves a thermostat's human-readable name
func (t *Thermostat) GetName() string {
	t.lock.RLock()
	defer t.lock.RUnlock()
	return t.name
}

// SetName assigns a thermostat's human-readable name
func (t *Thermostat) SetName(s string) {
	t.lock.Lock()
	defer t.lock.Unlock()
	t.name = s
}

// GetOperatingMode retrieves a thermostat's operating mode
func (t *Thermostat) GetOperatingMode() OperatingMode {
	t.lock.RLock()
	defer t.lock.RUnlock()
	return t.operatingMode
}

// SetOperatingMode assigns a thermostat's operating mode
func (t *Thermostat) SetOperatingMode(mode OperatingMode) {
	t.lock.Lock()
	defer t.lock.Unlock()
	t.operatingMode = mode
}

// GetFanMode retrieves a thermostat's fan mode
func (t *Thermostat) GetFanMode() FanMode {
	t.lock.RLock()
	defer t.lock.RUnlock()
	return t.fanMode
}

// SetFanMode assigns a thermostat's fan mode
func (t *Thermostat) SetFanMode(mode FanMode) {
	t.lock.Lock()
	defer t.lock.Unlock()
	t.fanMode = mode
}

// GetHeatPoint retrieves the target temperature a thermostat is set to heat to
func (t *Thermostat) GetHeatPoint() temp.Temp {
	t.lock.RLock()
	defer t.lock.RUnlock()
	return t.heatPoint
}

// SetHeatPoint sets the target temperature a thermostat is set to heat to
func (t *Thermostat) SetHeatPoint(heatPoint temp.Temp) {
	t.lock.Lock()
	defer t.lock.Unlock()
	t.heatPoint = heatPoint
}

// GetCoolPoint retrieves the target temperature a thermostat is set to cool to
func (t *Thermostat) GetCoolPoint() temp.Temp {
	t.lock.RLock()
	defer t.lock.RUnlock()
	return t.coolPoint
}

// SetCoolPoint sets the target temperature a thermostat is set to cool to
func (t *Thermostat) SetCoolPoint(coolPoint temp.Temp) {
	t.lock.Lock()
	defer t.lock.Unlock()
	t.coolPoint = coolPoint
}

// GetCurrentTemp retrieves the current temperature of a thermostat
func (t *Thermostat) GetCurrentTemp() temp.Temp {
	// Geometric mean of temperature distribution
	const average = 70

	// Standard Deviation of temperature distribution
	const deviation = 10

	return temp.Fahrenheit(rand.NormFloat64()*deviation + average)
}

// MarshalJSON implements the json.Marshaller interface
func (t *Thermostat) MarshalJSON() ([]byte, error) {
	t.lock.RLock()
	defer t.lock.RUnlock()

	v := struct {
		ID            uint32        `json:"id"`
		Name          string        `json:"name"`
		CurrentTemp   temp.Temp     `json:"currentTemp"`
		OperatingMode OperatingMode `json:"operatingMode"`
		HeatPoint     temp.Temp     `json:"heatPoint"`
		CoolPoint     temp.Temp     `json:"coolPoint"`
		FanMode       FanMode       `json:"fanMode"`
	}{
		ID:            t.id,
		Name:          t.name,
		CurrentTemp:   t.GetCurrentTemp(),
		OperatingMode: t.operatingMode,
		HeatPoint:     t.heatPoint,
		CoolPoint:     t.coolPoint,
		FanMode:       t.fanMode,
	}

	return json.MarshalIndent(v, "", "  ")
}

license: Unlicense


text:
# Copyright (c) 2013-2014 LG Electronics, Inc.

# LevelDB library for db8 package
#
# At present this package only installs the LevelDB code
# itself (shared libraries, .so in the dev package),
# documentation and headers.
#

SECTION = "libs"
DESCRIPTION = "LevelDB is a fast key-value storage library that provides an ordered mapping from string keys to string values"
HOMEPAGE = "http://leveldb.googlecode.com"
LICENSE = "BSD-3-Clause"
LIC_FILES_CHKSUM = "file://LICENSE;md5=92d1b128950b11ba8495b64938fc164d"

SRC_URI = "http://${BPN}.googlecode.com/files/${BP}.tar.gz \
    file://explicitly.disable.tcmalloc.patch \
"
SRC_URI[md5sum] = "e91fd7cbced8b84e21f357a866ad226a"
SRC_URI[sha256sum] = "d7c4ec571ef2ee9719f31db06344a1eba495e6abeeac1bc349d0d38a911c6680"

do_compile() {
    # do not use oe_runmake. oe_runmake pass to make compilation arguments and override
    # leveldb makefile variable CFLAGS and broke leveldb build.
    CFLAGS="${CFLAGS}" make || die
}

do_install() {
    install -d ${D}${libdir}
    oe_libinstall -C ${S} -so libleveldb ${D}${libdir}
    install -d ${D}${includedir}/leveldb
    install -m 644 ${S}/include/leveldb/*.h ${D}${includedir}/leveldb/
}

repository: nizovn/meta-webos-ports

repo_name: nizovn/meta-webos-ports