2019-09-17-anl.bib

@inproceedings{bae_benefits_2017,
	address = {Charlotte, North Carolina},
	title = {Benefits of {Siting} a {Borehole} {Repository} at a {Non}-operating {Nuclear} {Facility}},
	abstract = {This work evaluates a potential solution for two pressing
matters in the viability of nuclear energy: spent fuel disposal
and power plants that no longer operate. The potential benefits
of siting a borehole repository at a shut down nuclear power
plant facility are analyzed from the perspective of myriad stake-
holders. This assessment indicates that integrated siting will
make economic use of the shut down power plant, take advan-
tage of spent fuel handling infrastructure at those sites, mini-
mize transportation costs, expedite emptying the crowded spent
fuel storage pools accross the country, and will do so at sites
more likely to have consenting communities.},
	booktitle = {Proceedings of the {International} {High} {Level} {Radioactive} {Waste} {Management} {Conference}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Roy, William and Huff, Kathryn D.},
	month = apr,
	year = {2017}
}

@inproceedings{bae_synergistic_2017,
	address = {Washington, D.C.},
	title = {Synergistic {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union}},
	abstract = {The French strategy recommended by 2012-2015 Commission
Nationale d{\textquoteright}Evaluation reports [1] emphasizes preparation
for a transition from Light Water Reactors (LWRs) to
Sodium-Cooled Fast Reactors (SFRs). This paper uses Cyclus
to explore the feasibility of using Used Nuclear Fuel (UNF)
from other EU nations for French transition into a SFR fleet
without additional construction of LWRs. A Cyclus simulation
is run from 1950 to 2160 for EU to track the UNF mass
and to determine the necessary reprocessing and mixed oxide
(MOX) fabrication capacity to support the transition into
SFRs. The study concludes that France can avoid deployment
of additional LWRs by accepting UNF from other EU nations.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Winter} {Conference}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Huff, Kathryn and Singer, Clifford},
	month = oct,
	year = {2017},
	file = {europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/KEJMSZTE/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/LGFAP2BG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/MKKTZAGM/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/NLNAKMUG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/ZP787VN4/europe_nuclear_paper.pdf:application/pdf}
}

@inproceedings{huff_current_2017,
	address = {Seoul, South Korea},
	title = {Current {Status} of {Predictive} {Transition} {Capability} in {Fuel} {Cycle} {Simulation}},
	abstract = {Nuclear fuel cycle simulation scenarios are most naturally described as 
constrained objective functions. The objectives are often systemic 
demands such as ``achieve 1\% growth for total electricity production 
and reach 10\% uranium utilization''. The constraints take 
the form of nuclear fuel cycle technology availability 
(``reprocessing begins after 2025 and fast reactors first become 
available in 2050'').

To match the natural constrained objective form of the scenario 
definition, NFC simulators must bring demand responsive 
deployment decisions into the dynamics of the simulation logic.

In particular, a NFC simulator should have the 
capability to deploy supporting fuel cycle facilities to enable 
a demand to be met. Take, for instance, the standard once through fuel 
cycle. Reactors may be deployed to meet a objective power demand. 
However, new mines, mills, and enrichment facilities will also need to be 
deployed to ensure that reactors have sufficient fuel to produce power.  
In many simulators, the unrealistic solution to this problem is to 
simply have infinite capacity support facilities. Alternatively, 
detailing the deployment timeline of all facilities becomes the 
responsibility of the user.

The authors seek to identify the most flexible, general, and performant 
algorithms applicable to this modeling challenge.  Accordingly, a review was 
conducted of current NFC simulation tools to determine the 
current capabilites for demand-driven and transition scenarios. 
Additionally, the authors investigated promising algorithmic
innovations that have been successful for similar applications in other domains
such as economics and industrial engineering.},
	booktitle = {Proceedings of {Global} 2017},
	author = {Huff, Kathryn D. and Bae, Jin Whan and Mummah, Kathryn A. and Flanagan, Robert R. and Scopatz, Anthony M.},
	month = sep,
	year = {2017},
	file = {Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:/Users/khuff/Zotero/storage/CDQJ8KB8/Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:application/pdf}
}

@article{rykhlevskii_arfc/saltproc:_2018,
	title = {arfc/saltproc: {Code} for online reprocessing simulation of molten salt reactor with external depletion solver {SERPENT}},
	shorttitle = {arfc/saltproc},
	url = {https://zenodo.org/record/1196455#.WqrE_BPwaA0},
	doi = {10.5281/zenodo.1196455},
	abstract = {The script is re-run SERPENT 2 burnup simulation, and after each step removes target isotopes with specific efficiency, keep number density of target isotopes constant and keep track of Pa-233 --{\textgreater} U-233 decaying in the separate tank.},
	urldate = {2018-03-15},
	journal = {Zenodo},
	author = {Rykhlevskii, Andrei and Bae, Jin Whan and Huff, Kathryn},
	month = mar,
	year = {2018},
	doi = {10.5281/zenodo.1196455},
	keywords = {Fuel cycle, MSBR, MSR, online refueling, online reprocessing, salt separations, salt treatment, thorium cycle},
	file = {Zenodo Snapshot:/Users/khuff/Zotero/storage/Z6YA3XBL/1196455.html:text/html;Zenodo Snapshot:/Users/khuff/Zotero/storage/7YGYH6A6/1196455.html:text/html}
}

@inproceedings{chee_numerical_2018,
	address = {Gainesville, FL, United States},
	title = {Numerical {Experiments} for testing {Demand}-{Driven} {Deployment} {Algorithms}},
	abstract = {For many fuel cycle simulators, it is currently up to the user to define a deployment scheme for each component of the fuel cycle to avoid gaps in the supply chain. This same goal could also be achieved by setting all the facility{\textquoteright}s ca- pacities to infinity. However, this does not reflect real-world conditions [1]. To address this gap in capability of fuel cycle simulators, the Demand-Driven Cycamore Archetype project (NEUP-FY16-10512) is developing prediction algorithms to give Cyclus demand-driven deployment capabilities. This means that Cyclus will have the capability to deploy sup- porting fuel cycle facilities to meet front-end and back-end demands of the fuel cycle. The project is a collaboration between the University of Illinois Urbana-Champaign and the University of South Carolina. This paper will discuss the numerical experiments required to test the various prediction algorithms designed for the project. In particular, this work describes tests for the non-optimizing algorithm.},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2018 {National} {Student} {Conference},},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D.},
	month = apr,
	year = {2018},
	file = {Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:/Users/khuff/Zotero/storage/ZWG7WHKJ/Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:application/pdf;Fulltext:/Users/khuff/Zotero/storage/8729QICM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf;GwendolynChee-ansstuconf2018.pdf:/Users/khuff/Zotero/storage/Z6KJXWVH/GwendolynChee-ansstuconf2018.pdf:application/pdf;GwendolynChee-ansstuconf2018.pptx:/Users/khuff/Zotero/storage/3AMPECLL/GwendolynChee-ansstuconf2018.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation;Snapshot:/Users/khuff/Zotero/storage/7I6MM7HM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf}
}

@article{bae_arfc/transition-scenarios:_2018,
	series = {{GitHub}},
	title = {arfc/transition-scenarios: {Synergistic} {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union} v2.0.0},
	shorttitle = {arfc/transition-scenarios},
	url = {https://doi.org/10.5281/zenodo.1210302},
	doi = {10.5281/zenodo.1210302},
	abstract = {This release contains code to reproduce the plots used in the paper Synergistic Spent Nuclear Fuel Dynamics Within the European Union by Jin Whan Bae, Clifford Singer, Kathryn Huff},
	urldate = {2018-04-03},
	journal = {Zenodo},
	author = {Bae, Jin Whan and Park, Gyu Tae and Huff, Katy and Chee, Gwendolyn},
	month = mar,
	year = {2018},
	doi = {10.5281/zenodo.1210302},
	keywords = {agent-based, european union, simulation, spent nuclear fuel, Transition},
	file = {Zenodo Snapshot:/Users/khuff/Zotero/storage/CENLDTVM/1210302.html:text/html}
}

@techreport{bae_numerical_2018,
	address = {Urbana, IL},
	type = {Graduate {Report}},
	title = {Numerical {Experiments} for {Verifying} {Demand} {Driven} {Deployment} {Algorithms}},
	url = {https://github.com/arfc/ddca_numerical_exp},
	abstract = {For many fuel cycle simulations, it is currently up to the user to define a deployment scheme, or facility parameters, to make sure that there{\textquoteright}s no gap in the supply chain. Or, the same goal is achieved by setting the facility capacity to infinity, which does not reflect real-world conditions.
The Demand-Driven Cycamore Archetype project (NEUP-FY16-10512) aims to develop Cycamore demand-driven deployment capabilities. The developed algorithm, in the form of Cyclus Institution agent, deploys Facilities to meet the front-end and back-end demands of the fuel cycle.
This report describes numerical tests for non-optimizing, deterministic- optimizing and stochastic-optimizing prediction algorithms.
These prediction models are being developed by the University of South Carolina. In this report, we discuss numerical experiments for testing the non-optimizing, deterministic optimizing and stochastic optimizing meth- ods. The numerical experiments will be designed for both the once through nuclear fuel cycle and advanced fuel cycles.},
	number = {UIUC-ARFC-2018-01},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan and Chee, Gwendolyn and Huff, Kathryn},
	month = apr,
	year = {2018},
	keywords = {arfc, report},
	pages = {0--21},
	file = {Bae et al. - 2018 - Numerical Experiments for Verifying Demand Driven .pdf:/Users/khuff/Zotero/storage/5X9YWIQW/Bae et al. - 2018 - Numerical Experiments for Verifying Demand Driven .pdf:application/pdf}
}

@misc{rykhlevskii_fuel_2018,
	address = {Oak Ridge, TN, United States},
	type = {Poster},
	title = {Fuel {Cycle} {Performance} of {Fast} {Spectrum} {Molten} {Salt} {Reactor} {Designs}},
	abstract = {This poster shows progress in fuel cycle performance evaluation for 4 different fast molten salt reactors.},
	language = {English},
	author = {Rykhlevskii, Andrei},
	collaborator = {Betzler, Benjamin and Bae, Jin Whan and Huff, Kathryn},
	month = aug,
	year = {2018}
}

@article{bae_arfc/transition-scenarios:_2018-1,
	title = {arfc/transition-scenarios: {Standardized} {Verification} of the {Cyclus} {Fuel} {Cycle} {Simulator}},
	volume = {GitHub},
	url = {https://doi.org/10.5281/zenodo.1419110},
	doi = {10.5281/zenodo.1419110},
	abstract = {This release contains code and Cyclus input files to reproduce the plots used in the paper Standardized Verification of the Cyclus Fuel Cycle Simulator by Jin Whan Bae, Joshua L. Peterson-Droogh, and Kathryn D. Huff.},
	journal = {Zenodo},
	author = {Bae, Jin Whan and Park, Gyutae and Chee, Gwendolyn and Huff, Kathryn and Kennelly, Tyler and Speaks, PEP8 and Wilson, Paul and Scopatz, Anthony},
	month = sep,
	year = {2018}
}

@inproceedings{chee_validation_2018,
	address = {Orlando, FL},
	title = {Validation of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}},
	shorttitle = {Fuel {Cycle} {Analysis}},
	abstract = {Cyclus, a nuclear fuel cycle simulator, was used to simulate the United States{\textquoteright} nuclear fuel cycle from 1967 through 2013. The spent nuclear spent nuclear fuel (SNF) inventory from the Cyclus simulation was compared to the SNF inventory from the Department of Energy (DOE) sponsored Used Nuclear Fuel Storage, Transportation \& Disposal Analysis Resource and Data System (UNFST\&DARDS) Unified Database (UDB). The UDB provides comprehensive and consistent technical data on reactor sites and SNF from the beginning of nuclear reactor operation in the United States (US) until 2013. This comparison between Cyclus and UDB establishes a realistic validation of Cyclus{\textquoteright} capability to produce total spent fuel mass and accurate isotopic compositions that closely match reality.},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting} 2018},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Park, Gyutae and Huff, Kathryn D.},
	month = nov,
	year = {2018},
	file = {Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:/Users/khuff/Zotero/storage/PE67YJBQ/Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:application/pdf;Gwendolyn-Chee-ANSWinter2018.pdf:/Users/khuff/Zotero/storage/IYYD7F3R/Gwendolyn-Chee-ANSWinter2018.pdf:application/pdf}
}

@misc{rykhlevskii_advanced_2018,
	address = {Urbana, IL},
	type = {Seminar},
	title = {Advanced {Online} {Reprocessing} {Simulation} of {Thorium}-{Fueled} {Molten} {Salt} {Breeder} {Reactor}},
	abstract = {This poster shows progress in fuel cycle performance evaluation for 4 different fast molten salt reactors.},
	language = {English},
	author = {Rykhlevskii, Andrei},
	collaborator = {Huff, Kathryn and Bae, Jin Whan and Huff, Kathryn},
	month = apr,
	year = {2018}
}

@misc{bae_arfc/transition-scenarios:_2018-2,
	title = {arfc/transition-scenarios: {Synergistic} {Resubmission}},
	shorttitle = {arfc/transition-scenarios},
	url = {https://zenodo.org/record/2123465#.XA2TTBNKirw},
	abstract = {This release contains the code for reproducing the paper Synergistic Spent Nuclear Fuel Dynamics Within the European Union as re-submitted on December 9, 2018. Simulations were rerun as inspired by the reviews of that paper.},
	urldate = {2018-12-09},
	publisher = {Zenodo},
	author = {Bae, Jin Whan and Chee, Gwendolyn and Huff, Kathryn and Kennelly, Tyler and {PEP8 Speaks} and Wilson, Paul and Scopatz, Anthony},
	month = dec,
	year = {2018},
	doi = {10.5281/zenodo.2123465},
	file = {Zenodo Snapshot:/Users/khuff/Zotero/storage/WY9MV79E/2123465.html:text/html}
}

@misc{bae_impact_2018,
	address = {Orlando, FL},
	type = {Poster},
	title = {Impact of {Composition} {Approximation} on {Simulated} {Nuclear} {Fuel} {Cycle} {Metrics}},
	url = {http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf},
	author = {Bae, Jin Whan},
	collaborator = {Joshua, Peterson-Droogh and Huff, Kathryn D.},
	month = nov,
	year = {2018}
}

@article{rykhlevskii_modeling_2019,
	title = {Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor},
	volume = {128},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919300350},
	doi = {10.1016/j.anucene.2019.01.030},
	abstract = {In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. To further develop these MSR concepts, researchers need simulation tools for analyzing liquid-fueled MSR depletion and fuel processing. However, most contemporary nuclear reactor physics software is unable to perform high-fidelity full-core depletion calculations for a reactor design with online reprocessing. This paper introduces a Python package, SaltProc, which couples with the Monte Carlo code, SERPENT2 to simulate MSR online reprocessing by modeling the changing isotopic composition of MSR fuel salt. This work demonstrates SaltProc capabilities for a full-core, high-fidelity model of the commercial Molten Salt Breeder Reactor (MSBR) concept and verifies these results to results in the literature from independent, lower-fidelity analyses.},
	urldate = {2019-01-25},
	journal = {Annals of Nuclear Energy},
	author = {Rykhlevskii, Andrei and Bae, Jin Whan and Huff, Kathryn D.},
	month = jun,
	year = {2019},
	keywords = {agent based modeling, Depletion, Finite elements, Hydrologic contaminant transport, Molten salt breeder reactor, Molten salt reactor, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Online reprocessing, Parallel computing, Python, Reactor physics, repository, Salt treatment, Simulation, Systems analysis},
	pages = {366--379},
	file = {Rykhlevskii et al. - 2018 - Modeling and Simulation of Online Reprocessing in .pdf:/Users/khuff/Zotero/storage/Q5ABM9YG/Rykhlevskii et al. - 2018 - Modeling and Simulation of Online Reprocessing in .pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/8V55B4PR/Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/HJSJARBI/Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/P6PJ667C/S0306454919300350.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/W5RDKFMS/S0306454919300350.html:text/html}
}

@article{bae_standardized_2019,
	title = {Standardized verification of the {Cyclus} fuel cycle simulator},
	volume = {128},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919300179},
	doi = {10.1016/j.anucene.2019.01.014},
	abstract = {Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of Cyclus, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, Cyclus demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the Cycamore reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.},
	urldate = {2019-01-25},
	journal = {Annals of Nuclear Energy},
	author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.},
	month = jun,
	year = {2019},
	keywords = {agent based modeling, C, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Parallel computing, Reactor physics, repository, Simulation, Systems analysis, Verification},
	pages = {288--291},
	file = {Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:/Users/khuff/Zotero/storage/T6Q5G2AW/Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/UXQWH3GA/Bae et al. - 2019 - Standardized verification of the Cyclus fuel cycle.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/WFFQBL3B/S0306454919300179.html:text/html}
}

@article{huff_current_2017-1,
	title = {Current {Status} of {Predictive} {Transition} {Capability} in {Fuel} {Cycle} {Simulation}},
	abstract = {This study has identified flexible, general, and performant algorithms available for application to simulating demand-driven deployment of nuclear fuel cycle facility capacity in a fuel cycle simulator. Accordingly, a review of current Nuclear Fuel Cycle (NFC) simulation tools was conducted to determine their current capabilities for demand-driven and transition scenarios. Additionally, the authors investigated promising algorithmic innovations that have been successful for similar applications in other domains such as economics and industrial engineering Finally, the applicability of such algorithms in the context of challenging nuclear fuel cycle simulation questions has been described.},
	language = {en},
	author = {Huff, Kathryn D and Bae, Jin Whan and Flanagan, Robert R and Scopatz, Anthony M},
	year = {2017},
	pages = {11},
	file = {Huff et al. - Current Status of Predictive Transition Capability.pdf:/Users/khuff/Zotero/storage/LE3726S6/Huff et al. - Current Status of Predictive Transition Capability.pdf:application/pdf}
}

@inproceedings{chee_demonstration_2019,
	address = {Seattle, WA, United States},
	title = {Demonstration of {Demand}-{Driven} {Deployment} {Capabilities} in {Cyclus}},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2019 {Global} {Conference}},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D. and Flanagan, Robert R. and Fairhurst, Roberto},
	month = sep,
	year = {2019}
}

@inproceedings{flanagan_methods_2019,
	address = {Seattle, WA, United States},
	title = {Methods for {Automated} {Fuel} {Cycle} {Facility} {Deployment}},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2019 {Global} {Conference}},
	publisher = {American Nuclear Society},
	author = {Flanagan, Robert R. and Bae, Jin Whan and Huff, Kathryn D. and Chee, Gwendolyn J. and Fairhurst, Roberto},
	month = sep,
	year = {2019}
}

@article{bae_deep_2019,
	title = {Deep {Learning} {Approach} to {Nuclear} {Fuel} {Transmutation} in a {Fuel} {Cycle} {Simulator}},
	journal = {Submitted},
	author = {Bae, Jin Whan and Chee, Gwendolyn J., Chee and Huff, Kathryn D.},
	year = {2019},
	note = {github.com/jbae11/depletion\_rom}
}

@inproceedings{chee_simulation_2019,
	address = {Phoenix, AZ},
	title = {Simulation of {Spent} {Nuclear} {Fuel} loading into a {Final} {Waste} {Repository}},
	booktitle = {{WM} {Symposia} 2019 {Proceedings}},
	author = {Chee, Gwendolyn J. and Huff, Kathryn D.},
	month = apr,
	year = {2019},
	file = {Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:/Users/khuff/Zotero/storage/8BZG9D2S/Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:application/pdf}
}

@article{bae_synergistic_2019,
	title = {Synergistic spent nuclear fuel dynamics within the {European} {Union}},
	volume = {114},
	issn = {0149-1970},
	url = {http://www.sciencedirect.com/science/article/pii/S014919701930037X},
	doi = {10.1016/j.pnucene.2019.02.001},
	abstract = {The French 2012{\textendash}2015 Commission Nationale d{\textquoteright}Evaluation Reports emphasize preparation for a transition from Light Water Reactors (LWRs) to Sodium-Cooled Fast Reactors (SFRs). We used the Cyclus nuclear fuel cycle simulator to explore the feasibility of enabling a French transition to an SFR fleet by using Used Nuclear Fuel (UNF) from other European Union (EU) nations. A Cyclus simulation captured nuclear power deployment in the EU from 1970 to 2160. In this simulation, France begins its planned transition to SFRs as existing LWRs are decommissioned. These SFRs are fueled with UNF accumulated by other EU nations and reprocessed in France. The impact of reactor lifetime extensions and SFR breeding ratios on time-to-transition were investigated with additional simulations. These simulations demonstrate that France can avoid deployment of additional LWRs by accepting UNF from other EU nations, that lifetime extensions delay time-to-transition, and improved breeding ratios are not particularly impactful.},
	urldate = {2019-04-15},
	journal = {Progress in Nuclear Energy},
	author = {Bae, Jin Whan and Singer, Clifford E. and Huff, Kathryn D.},
	month = jul,
	year = {2019},
	keywords = {agent based modeling, Agent-based, European union, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Parallel computing, Reactor physics, repository, Simulation, Spent nuclear fuel, Systems analysis, Transition},
	pages = {1--12},
	file = {Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:/Users/khuff/Zotero/storage/3QBIMRIH/Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/FUTLQJAP/Bae et al. - 2019 - Synergistic spent nuclear fuel dynamics within the.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/E9FXRY45/S014919701930037X.html:text/html}
}

@inproceedings{bae_impact_2018-1,
	address = {Orlando, FL},
	title = {Impact of {Composition} {Approximation} on {Simulated} {Nuclear} {Fuel} {Cycle} {Metrics}},
	url = {http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.},
	month = nov,
	year = {2018}
}

@mastersthesis{bae_fuel_2018,
	address = {Urbana, IL},
	title = {Fuel cycle transition simulation capabilities in {CYCLUS}},
	copyright = {Copyright 2018 Jin Whan Bae},
	url = {https://www.ideals.illinois.edu/handle/2142/102517},
	abstract = {Recent interest in advanced reactors and the following need for techno-economic transitions has increased the demand for tools necessary to model complex nuclear fuel cycles (NFCs) and advanced reactor technologies. This thesis demonstrates the capability of CYCLUS , the agent-based fuel cycle simulator, to model, simulate, and analyze real-life fuel cycle transition scenarios. I introduce new methods and tools that use various databases to model and simulate real-world nuclear fuel cycle transition scenarios involving advanced reactor technologies.

The work in this thesis contains: (1) benchmarking Cyclus to other nuclear fuel cycle simulators (NFC simulators); (2) developing new methods and tools necessary for modeling and simulating real-world fuel cycle transition scenarios; (3) simulation of both domestic and international nuclear technology transitions.

The methods and tools developed for such capabilities include: (1) modeling and simulating past and current nuclear fleets using historic nuclear reactor operations database; (2) modeling individual reactors and their operating history to calculate nuclear material inventory; (3) modeling Molten Salt Reactor (MSR) behavior in a large-scale fuel cycle simulation.

Benchmark work shows that CYCLUS results coincide with results from other NFC simulators with minor differences due to modeling choices. Additionally, this thesis demonstrates the CYCLUS capability to effectively model and simulate real-life NFC transition scenarios that involve advanced reactor technologies such as MSRs.},
	language = {en},
	urldate = {2019-06-13},
	school = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan},
	month = dec,
	year = {2018},
	file = {Full Text PDF:/Users/khuff/Zotero/storage/NAP77Q4U/Bae - 2018 - Fuel cycle transition simulation capabilities in C.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/RMWZTFLG/102517.html:text/html}
}

@misc{chee_demand_2019,
	address = {Champaign, IL},
	type = {Workshop},
	title = {Demand {Driven} {Deployment} {Capabilities} in {Cyclus}},
	abstract = {For many fuel cycle simulators, it is currently up to the user to define a deployment scheme of supporting facilities or provide an infinite inventory of commodities to ensure that there is no gap in the supply chain. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand responsive deployment decisions into the dynamics of the simulation logic. In this work, we develop demand driven deployment capabilities in Cyclus, d3ploy. User-controlled capabilities such as supply/ capacity buffers, constraint deployment, prediction algorithms, and installed capacity deployment were introduced in d3ploy to give a user the tools to minimize commodity undersupply in a simulation. We demonstrate d3ploy{\textquoteright}s capability to automatically deploy fuel cycle facilities to meet various types of user-defined power demands: constant, linearly increasing, and sinusoidal.},
	author = {Chee, Gwendolyn J.},
	collaborator = {Flanagan, Robert R. and Huff, Kathryn D},
	month = jun,
	year = {2019},
	file = {2019-chee-twofcs-pres.pdf:/Users/khuff/Zotero/storage/V95BLIN6/2019-chee-twofcs-pres.pdf:application/pdf;2019-chee-twofcs-pres.pptx:/Users/khuff/Zotero/storage/N49L9PAI/2019-chee-twofcs-pres.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation}
}

@techreport{chee_transition_2019,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Transition {Scenario} {Demonstrations} of {CYCAMORE} {Demand} {Driven} {Deployment} {Capabilities}},
	shorttitle = {Contract {DE}-{NE}0008567},
	url = {https://zenodo.org/record/3354507#.XT9MApNKirw},
	abstract = {In many fuel cycle simulators, the user must define a deployment scheme for all supporting facilities to avoid supply chain gaps. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand-responsive deployment decisions into the dynamics of the simulation logic. Thus, a next-generation NFC simulator should predictively and automatically deploy fuel cycle facilities to meet a user-defined power demand. CYCLUS is an agent-based nuclear fuel cycle simulation framework [4]. In CYCLUS, each entity (i.e. Region, Institution, or Facility) in the fuel cycle is an agent. Region agents represent geographical or political areas that institution and facility agents can be grouped into. Institution agents control the deployment and decommission of facility agents and represents legal operating organizations such as a utility, government, etc. Facility agents represent nuclear fuel cycle facilities. CYCAMORE provides agents to represent process physics of various components in the nuclear fuel cycle (e.g. mine, fuel enrichment facility, reactor). The Demand-Driven CYCAMORE Archetypes project (NEUP-FY16-10512) aims to develop CYCLUS{\textquoteright} demand-driven deployment capabilities. This capability is added as a CYCLUS Institution agent that deploys facilities to meet the front-end and back-end fuel cycle demands based on a user-defined commodity demand. This demand-driven deployment capability is called d3ploy. In this paper, we explain the capabilities of d3ploy and demonstrate how d3ploy minimizes undersupply of all commodities in a few simulations while meeting key simulation constraints. Constant, linearly increasing, and sinusoidal power demand transition scenarios are demonstrated. Insights are discussed to inform parameter input decisions for future work in setting up larger transition scenarios that include many facilities. And finally, the more complex transition scenarios are demonstrated.},
	language = {english},
	number = {UIUC-ARFC-2019-03},
	urldate = {2019-07-29},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn and Fairhurst, Roberto and Huff, Kathryn},
	month = jun,
	year = {2019},
	doi = {10.5281/zenodo.3354507},
	keywords = {arfc, cyclus, nuclear fuel cycle, report},
	pages = {1--23},
	file = {Chee - 2019 - Transition Scenario Demonstrations of ARFC CYCAMOR.pdf:/Users/khuff/Zotero/storage/RV5PZF3E/Chee - 2019 - Transition Scenario Demonstrations of ARFC CYCAMOR.pdf:application/pdf;Zenodo Full Text PDF:/Users/khuff/Zotero/storage/FZWMCLYT/Gwendolyn Chee et al. - 2019 - Transition Scenario Demonstrations of CYCAMORE Dem.pdf:application/pdf}
}

@misc{rykhlevskii_fuel_2019,
	address = {Portland, OR, United States},
	type = {Conference},
	title = {Fuel {Cycle} {Performance} of {Fast} {Spectrum} {Molten} {Salt} {Reactor} {Designs}},
	abstract = {This presentation shows progress in fuel cycle performance evaluation for 4 different fast molten salt reactors.},
	language = {English},
	author = {Rykhlevskii, Andrei},
	collaborator = {Betzler, Benjamin and Bae, Jin Whan and Huff, Kathryn},
	month = aug,
	year = {2019},
	file = {Rykhlevskii - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:/Users/khuff/Zotero/storage/3SIXCH7U/Rykhlevskii - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:application/pdf}
}

@inproceedings{huff_dynamic_2013,
	address = {Atlanta, GA, United States},
	title = {Dynamic {Determination} of {Thermal} {Repository} {Capacity} {For} {Fuel} {Cycle} {Analysis}},
	volume = {108},
	abstract = {An algorithm and supporting database for rapid thermal
repository capacity calculation implemented in Cyder, a soft-
ware library for coupled thermal and hydrologic repository per-
formance analysis, is described. Integration of Cyder with the
Cyclus fuel cycle simulator is also described. Finally, a proof
of principle demonstration is presented in which the rapid cal-
culation method described here is compared with results of a
more detailed model.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Bara, Alexander T.},
	month = jun,
	year = {2013},
	pages = {123--126},
	file = {trans_v108_n1_pp123-126 (1).pdf:/Users/khuff/Zotero/storage/3I456PBS/trans_v108_n1_pp123-126 (1).pdf:application/pdf}
}

@inproceedings{huff_extensions_2014,
	address = {Anaheim, CA, United States},
	series = {Fuel {Cycle} {Options} {Analysis} -- {III}},
	title = {Extensions to the {Cyclus} {Ecosystem} {In} {Support} of {Market}-{Driven} {Transition} {Capability}},
	abstract = {The C YCLUS Fuel Cycle Simulator [1] is a framework
for assessment of nuclear fuel cycle options. While C Y -
CLUS has previously been capable of system transitions
from the current fuel cycle strategy to a future option, those
transitions have never previously been driven by market
forces in the simulation. This summary describes a set
of libraries [2] that have been contibuted to the C YCLUS
framework to enable a market-driven transition analysis.
This simulation framework is incomplete without a suite
of dynamically loadable libraries representing the process
physics of the nuclear fuel cycle (i.e. mining, fuel fabri-
cation, chemical processing, transmutation, reprocessing,
etc.). Within Cycamore [3], the additional modules reposi-
tory within the C YCLUS ecosystem, provides some basic li-
braries to represent these processes. However, extension of
C YCLUS with new capabilities is community-driven, rely-
ing on contributions by user-developers. The libraries con-
tributed in this work are examples of such contributions.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Fratoni, Massimiliano and Greenberg, Harris},
	month = nov,
	year = {2014},
	note = {LLNL-PROC-656426},
	pages = {245--248},
	file = {huff_extensions_2014.pdf:/Users/khuff/Zotero/storage/MV2TCELS/huff_extensions_2014.pdf:application/pdf}
}

@article{carlsen_cycamore_2014,
	title = {Cycamore v1.0.0},
	url = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	doi = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	abstract = {Additional module for Cyclus, the nuclear fuel cycle simulator developed at the University of Wisconsin - Madison, supporting the modeling of innovative fuel cycles.},
	urldate = {2014-06-03},
	journal = {Figshare},
	author = {Carlsen, Robert W. and Gidden, Matthew and Huff, Kathryn and Opotowsky, Arrielle C. and Rakhimov, Olzhas and Scopatz, Anthony M. and Wilson, Paul},
	month = jun,
	year = {2014},
	note = {http://figshare.com/articles/Cycamore\_v1\_0\_0/1041829},
	keywords = {Nuclear Fuel Cycle, agent-based simulation},
	file = {cycamore_1.0.0:/Users/khuff/Zotero/storage/W2VGZTDV/Scopatz et al. - 2014 - Cycamore v1.0.0:application/zip;Figshare Download:/Users/khuff/Zotero/storage/WQD2B5KA/Scopatz et al. - 2014 - Cycamore v1.0.0:application/zip;Figshare Snapshot:/Users/khuff/Zotero/storage/N44XFGRX/Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html;Full Text (HTML):/Users/khuff/Zotero/storage/H56U7DUZ/Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html}
}

@article{carlsen_cyclus_2014,
	title = {Cyclus v1.0.0},
	url = {http://figshare.com/articles/Cyclus_v1_0_0/1041745},
	doi = {http://dx.doi.org/10.6084/m9.figshare.1041745},
	abstract = {Cyclus is the next-generation agent-based nuclear fuel cycle simulator, providing flexibility to users and developers through adynamic resource exchange solver and plug-in, user-developed agent framework.
The goal of Cyclus is to enable a broad spectrum of fuel cycle simulation while providing a low barrier to entry for new users and agent developers. Cyclus engages with potential module developers and encourages them to join a vibrant community in anexpanding ecosystem. Users and developers are always welcome and encouraged to use or contribute to the Cyclus project.},
	urldate = {2014-06-24},
	journal = {Figshare},
	author = {Carlsen, Robert W. and Gidden, Matthew and Huff, Kathryn and Opotowsky, Arrielle C. and Rakhimov, Olzhas and Scopatz, Anthony M. and Welch, Zach and Wilson, Paul},
	month = jun,
	year = {2014},
	note = {http://dx.doi.org/10.6084/m9.figshare.1041745},
	keywords = {Nuclear fuel cycle, agent-based simulation},
	file = {cyclus_1.0.0:/Users/khuff/Zotero/storage/HW2QA8MN/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;cyclus_1.0.0:/Users/khuff/Zotero/storage/BDXXRM7B/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Download:/Users/khuff/Zotero/storage/5MZCI93N/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Download:/Users/khuff/Zotero/storage/NN545PPD/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Snapshot:/Users/khuff/Zotero/storage/SEA6MHKH/1041745.html:text/html;Figshare Snapshot:/Users/khuff/Zotero/storage/T982H6ZW/1041745.html:text/html;Full Text (HTML):/Users/khuff/Zotero/storage/H2K87S9S/1041745.html:text/html;Full Text (HTML):/Users/khuff/Zotero/storage/QSIAAMM8/1041745.html:text/html}
}

@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.},
	language = {en},
	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},
	note = {arXiv: 1509.03604},
	keywords = {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, I.6.7, I.6.8, Nuclear fuel cycle, Simulation, Systems analysis, agent based modeling, Object orientation, and Science, Computer Science - Computational Engineering, Finance, nuclear engineering, simulation, Agent based modeling, Nuclear engineering},
	pages = {46--59},
	file = {arXiv\:1509.03604 PDF:/Users/khuff/Zotero/storage/4FI3T63Q/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/khuff/Zotero/storage/F9KVM9DZ/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/khuff/Zotero/storage/GN7WIP38/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;arXiv.org Snapshot:/Users/khuff/Zotero/storage/WQVTXAN2/1509.html:text/html;arXiv.org Snapshot:/Users/khuff/Zotero/storage/HXSDS7VW/1509.html:text/html;arXiv.org Snapshot:/Users/khuff/Zotero/storage/EVFA3LC6/1509.html:text/html;Fulltext:/Users/khuff/Zotero/storage/3IMCACE5/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;fundamentals.pdf:/Users/khuff/Zotero/storage/BRJECDWC/fundamentals.pdf:application/pdf;fundamentals.pdf:/Users/khuff/Zotero/storage/C6G4NQJH/fundamentals.pdf:application/pdf;Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:/Users/khuff/Zotero/storage/FAM6DNLV/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/E7DK64AA/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/63CHUQ54/login.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/EVBNKXMA/S0965997816300229.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/JCCZAZB3/S0965997816300229.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/275X4LV5/S0965997816300229.html:text/html;Snapshot:/Users/khuff/Zotero/storage/9DRDIPZV/S0965997816300229.html:text/html}
}

@techreport{doe_strategy_2013,
	address = {Washington D.C., United States},
	title = {Strategy for the {Management} and {Disposal} of {Used} {Nuclear} {Fuel} and {High}-{Level} {Radioactive} {Waste}},
	url = {http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste},
	urldate = {2013-02-01},
	institution = {United States Department of Energy},
	author = {{DOE}},
	month = jan,
	year = {2013},
	file = {2013 1-15 Nuclear_Waste_Report.pdf:/Users/khuff/Zotero/storage/P93IDV6R/2013 1-15 Nuclear_Waste_Report.pdf:application/pdf;doe_strategy_2013.pdf:/Users/khuff/Zotero/storage/GITPI2GM/doe_strategy_2013.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/RBC8D4NG/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste.html:text/html}
}

@techreport{wilson_adoption_2009,
	title = {The {Adoption} of {Advanced} {Fuel} {Cycle} {Technology} {Under} a {Single} {Repository} {Policy}},
	institution = {University of Wisconsin -- Madison},
	author = {Wilson, P.},
	year = {2009}
}

@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:/Users/khuff/Zotero/storage/FUJ5IKU7/Bell 1973 ORIGEN.pdf:application/pdf}
}

@misc{iaea_pris_2017,
	title = {{PRIS} - {Home}},
	url = {https://www.iaea.org/pris/},
	urldate = {2017-04-03},
	author = {IAEA},
	month = sep,
	year = {2017},
	file = {PRIS - Home:/Users/khuff/Zotero/storage/KJU7EXF4/pris.html:text/html;PRIS - Home:/Users/khuff/Zotero/storage/4H5378XB/home.html:text/html}
}

@inproceedings{bae_synergistic_2017,
	address = {Washington, D.C.},
	title = {Synergistic {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union}},
	abstract = {The French strategy recommended by 2012-2015 Commission
Nationale d{\textquoteright}Evaluation reports [1] emphasizes preparation
for a transition from Light Water Reactors (LWRs) to
Sodium-Cooled Fast Reactors (SFRs). This paper uses Cyclus
to explore the feasibility of using Used Nuclear Fuel (UNF)
from other EU nations for French transition into a SFR fleet
without additional construction of LWRs. A Cyclus simulation
is run from 1950 to 2160 for EU to track the UNF mass
and to determine the necessary reprocessing and mixed oxide
(MOX) fabrication capacity to support the transition into
SFRs. The study concludes that France can avoid deployment
of additional LWRs by accepting UNF from other EU nations.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Winter} {Conference}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Huff, Kathryn and Singer, Clifford},
	month = oct,
	year = {2017},
	file = {europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/KEJMSZTE/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/LGFAP2BG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/MKKTZAGM/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/NLNAKMUG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/khuff/Zotero/storage/ZP787VN4/europe_nuclear_paper.pdf:application/pdf}
}

@article{peterson_unf-st&dards_2017,
	title = {{UNF}-{ST}\&{DARDS} {Unified} {Database} and the {Automatic} {Document} {Generator}},
	volume = {199},
	number = {3},
	journal = {Nuclear Technology},
	author = {Peterson, Josh and van den Akker, Bret and Cumberland, Riley and Miller, Paul and Banerjee, Kaushik},
	year = {2017},
	pages = {310--319},
	file = {Fulltext:/Users/khuff/Zotero/storage/CUXQ46R8/00295450.2017.html:text/html;Peterson et al. - 2017 - UNF-ST&DARDS Unified Database and the Automatic Do.pdf:/Users/khuff/Zotero/storage/AJUWFE6I/Peterson et al. - 2017 - UNF-ST&DARDS Unified Database and the Automatic Do.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/ZTL5PK5U/00295450.2017.html:text/html}
}

@techreport{francis_reactor_2015,
	title = {Reactor {Fuel} {Isotopics} and {Code} {Validation} for {Nuclear} {Applications}},
	url = {http://www.osti.gov/servlets/purl/1185693/},
	language = {en},
	number = {ORNL/TM--2014/464, 1185693},
	urldate = {2018-05-23},
	author = {Francis, Matthew W. and Weber, Charles F. and Pigni, Marco T. and Gauld, Ian C.},
	month = feb,
	year = {2015},
	doi = {10.2172/1185693},
	file = {Francis et al. - 2015 - Reactor Fuel Isotopics and Code Validation for Nuc.pdf:/Users/khuff/Zotero/storage/HZLL88N2/Francis et al. - 2015 - Reactor Fuel Isotopics and Code Validation for Nuc.pdf:application/pdf}
}

@misc{noauthor_jupyter_nodate,
	title = {The {Jupyter} {Notebook} - {IPython}},
	url = {https://ipython.org/notebook.html},
	urldate = {2018-06-01},
	file = {The Jupyter Notebook {\textemdash} IPython:/Users/khuff/Zotero/storage/MG54KYIT/notebook.html:text/html}
}

@misc{ronacher_welcome_2018,
	title = {Welcome to {Jinja}2 - {Jinja}2 {Documentation} (2.10)},
	url = {http://jinja.pocoo.org/docs/2.10/},
	urldate = {2018-06-01},
	author = {Ronacher},
	year = {2018},
	file = {Welcome to Jinja2 {\textemdash} Jinja2 Documentation (2.10):/Users/khuff/Zotero/storage/3CE4W9UW/2.html:text/html}
}

@misc{chee_gwenchee/transition-scenarios_2018,
	title = {gwenchee/transition-scenarios : {Validation} of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}},
	shorttitle = {arfc/transition-scenarios},
	url = {https://zenodo.org/record/1287986},
	abstract = {This release contains code to reproduce the plots used in the conference summary Validation of Spent Nuclear Fuel Output by Cyclus, a Fuel Cycle Simulator Code},
	urldate = {2017-08-31},
	publisher = {Advanced Reactors and Fuel Cycles Research Group},
	author = {Chee, Gwendolyn and Park, Gyu Tae and Huff, Kathryn},
	month = jun,
	year = {2018},
	doi = {10.5281/zenodo.1287986}
}

@article{iaea_current_nodate,
	title = {Current {Trends} in {Nuclear} {Fuel} for {Power} {Reactors}},
	language = {en},
	author = {IAEA},
	pages = {11},
	file = {Current Trends in Nuclear Fuel for Power Reactors.pdf:/Users/khuff/Zotero/storage/X5R5RPFR/Current Trends in Nuclear Fuel for Power Reactors.pdf:application/pdf}
}

@misc{gehin_nuclear_2016,
	address = {Knoxville, TN, United States},
	title = {Nuclear {Power} {Reactors} - {An} {Example} of {Improvements} in {Reliability} and {Potential} for {Improvement}},
	url = {https://neutrons2.ornl.gov/conf/arw2015/presentations/B%20-%20Gehin%20-%20Nuclear%20Power%20Reactors%20%E2%80%93%20An%20Example%20of%20Improvements%20in%20Reliability%20and%20Potential%20for%20Improvement.pdf},
	urldate = {2018-06-10},
	author = {Gehin, Jess},
	month = apr,
	year = {2016},
	file = {B - Gehin - Nuclear Power Reactors {\textendash} An Example of Improvements in Reliability and Potential for Improvement.pdf:/Users/khuff/Zotero/storage/7KVMBDC7/B - Gehin - Nuclear Power Reactors {\textendash} An Example of Improvements in Reliability and Potential for Improvement.pdf:application/pdf}
}

@article{peterson_additional_2017,
	title = {Additional {Capability} {Being} {Developed} from {UNF}-{ST}\&{DARDS} {Unified} {Database}: {System} {Analysis} and {Fuel} {Cycle} {Option} {Analysis}},
	volume = {199},
	issn = {0029-5450, 1943-7471},
	shorttitle = {Additional {Capability} {Being} {Developed} from {UNF}-{ST}\&{DARDS} {Unified} {Database}},
	url = {https://www.tandfonline.com/doi/full/10.1080/00295450.2017.1354551},
	doi = {10.1080/00295450.2017.1354551},
	abstract = {The Used Nuclear Fuel Storage, Transportation \& Disposal Analysis Resource and Data System (UNF-ST\&DARDS) is being developed for the U.S. Department of Energy{\textquoteright}s Office of Nuclear Energy by the national laboratories. An important part of UNF-ST\&DARDS is the Unified Database (UDB), which contains information that can support a variety of activities including fuel storage, fuel transportation, and disposal-related system analysis. Currently, the main application of the UDB is to support evaluation of the characteristics of discharged spent nuclear fuel (SNF) from the U.S. commercial reactors. However, because of the extensive amount of data that has been collected and analyzed for UNFST\&DARDS, there are many more applications that can utilize the UDB including system analysis with the Next-Generation System Analysis Model (NGSAM) and fuel cycle analysis with fuel cycle simulation codes such as ORION. Going forward, NGSAM and fuel cycle transition analysis with ORION integrate UDB data wherever possible in the UDB{\textquoteright}s development plan. These advances in NGSAM and fuel cycle analysis can be used in conjunction with the UDB to help answer more complex questions about the optimization, utilization, storage, and eventual disposal of SNF.},
	language = {en},
	number = {3},
	urldate = {2018-08-15},
	journal = {Nuclear Technology},
	author = {Peterson, Josh and Olson, Chuck and St. Aubin, Jim and Craig, Brian},
	month = sep,
	year = {2017},
	pages = {320--329},
	file = {Peterson et al. - 2017 - Additional Capability Being Developed from UNF-ST&.pdf:/Users/khuff/Zotero/storage/Z5UEBNAP/Peterson et al. - 2017 - Additional Capability Being Developed from UNF-ST&.pdf:application/pdf}
}

@misc{eia_spent_2015,
	title = {Spent {Nuclear} {Fuel}},
	url = {https://www.eia.gov/nuclear/spent_fuel/ussnftab3.php},
	urldate = {2018-08-16},
	journal = {U.S. Energy Information Administration},
	author = {EIA},
	month = dec,
	year = {2015},
	file = {Table 3. Annual commercial spent fuel discharges and burnup:/Users/khuff/Zotero/storage/LVKAHR95/ussnftab3.html:text/html}
}

@misc{chee_arfc/transition-scenarios_2018,
	title = {arfc/transition-scenarios : {Validation} of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}},
	shorttitle = {arfc/transition-scenarios},
	abstract = {This release contains code to reproduce the plots used in the revised conference summary Validation of Spent Nuclear Fuel Output by Cyclus, a Fuel Cycle Simulator Code},
	urldate = {2017-08-31},
	publisher = {Advanced Reactors and Fuel Cycles Research Group},
	author = {Chee, Gwendolyn and Park, Gyu Tae and Huff, Kathryn},
	month = aug,
	year = {2018},
	doi = {10.5281/zenodo.1401495}
}

@article{wigeland_separations_2006,
	title = {Separations and {Transmutation} {Criteria} to {Improve} {Utilization} of a {Geologic} {Repository}},
	volume = {154},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT06-3},
	doi = {10.13182/NT06-3},
	abstract = {This paper describes the results of a study that uses the thermal performance of the repository to establish chemical separations and transmutation criteria for commercial spent nuclear fuel of benefit to a geologic repository, as measured by the allowable increase in utilization of repository space. The method for determining the chemical elements to be separated is based on the thermal performance of the repository. The important chemical elements are identified, the order of importance of the separated elements is established, and the relationship between the efficiency of the chemical separation and the resulting increase in utilization is determined. The proposed repository at Yucca Mountain is used as an example of a geologic repository for the purposes of illustrating the magnitude of the benefits that are possible and the implications for repository size and operation. This work is being done in support of the U.S. Department of Energy Advanced Fuel Cycle Initiative, where numerous reactor, processing, and recycling strategies are being examined to determine the impact on issues important to the viability of nuclear electricity generation, including the disposal of spent nuclear fuel and nuclear waste.},
	number = {1},
	urldate = {2018-09-06},
	journal = {Nuclear Technology},
	author = {Wigeland, Roald A. and Bauer, Theodore H. and Fanning, Thomas H. and Morris, Edgar E.},
	month = apr,
	year = {2006},
	keywords = {Geologic Repository, Spent-Fuel Processing, Thermal Limits},
	pages = {95--106},
	file = {Full Text PDF:/Users/khuff/Zotero/storage/G5IEE6U5/Wigeland et al. - 2006 - Separations and Transmutation Criteria to Improve .pdf:application/pdf;NT-Wigeland-Repository-Benefit.pdf:/Users/khuff/Zotero/storage/HI3B9NS8/NT-Wigeland-Repository-Benefit.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/L7MN8G4E/NT06-3.html:text/html}
}

@misc{noauthor_nuclear_nodate,
	title = {Nuclear fuel cycle {\textbar} {Slovensk{\'e}} elektr{\'a}rne},
	url = {https://www.seas.sk/nuclear-fuel-cycle},
	urldate = {2018-10-28},
	file = {Nuclear fuel cycle | Slovensk{\'e} elektr{\'a}rne:/Users/khuff/Zotero/storage/ZJXR9T3S/nuclear-fuel-cycle.html:text/html}
}

@misc{park_arfc/cycmap_2018,
	title = {arfc/cycmap : {Validation} of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}},
	shorttitle = {arfc/transition-scenarios},
	abstract = {This release contains code to reproduce the plots used in the conference presentation Validation of Spent Nuclear Fuel Output by Cyclus, a Fuel Cycle Simulator Code},
	urldate = {2017-08-31},
	publisher = {Advanced Reactors and Fuel Cycles Research Group},
	author = {Park, Gyu Tae and Huff, Kathryn and Huff, Kathryn},
	month = oct,
	year = {2018},
	doi = {10.5281/zenodo.1475436}
}

@techreport{nei_u.s._2018,
	title = {U.{S}. {Nuclear} {Generating} {Statistics}},
	url = {https://www.nei.org/resources/statistics/us-nuclear-generating-statistics},
	author = {NEI},
	month = apr,
	year = {2018}
}