bibliography.bib

@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{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},
	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;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{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{schneider_nfcsim_2004,
	title = {{NFCSim} {Scenario} {Studies} of {German} and {European} {Reactor} {Fleets}},
	url = {http://www.google.com/url?sa=t&source=web&cd=3&ved=0CCcQFjAC&url=http%3A%2F%2Fwww.iket.fzk.de%2Fcube%2Flib%2Ffiles%2Fcf87f8b74d3a0e02bb5a7e520b62a9a0.pdf&rct=j&q=NFCSim%20Scenario%20Studies%20of%20German%20and%20European%20Reactor%20Fleets&ei=Mn0UTsXSB9GJsAK67-DUDw&usg=AFQjCNHw-H29zWnlB3tiN4VL4Xl-SbJYmg&sig2=wGuk9I7N41Rz0lCmR_Lflw&cad=rja},
	institution = {LA-UR-04-4911, Los Alamos National Laboratory},
	author = {Schneider, E. and Knebel, M. and Schwenk-Ferrero, W.},
	year = {2004}
}

@phdthesis{gidden_agent-based_2015,
	address = {Madison, WI, United States},
	type = {{PhD} {Thesis}},
	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},
	author = {Gidden, Matthew J.},
	month = mar,
	year = {2015},
	file = {gidden_agent-based_2015.pdf:/Users/khuff/Zotero/storage/E6J9VKJM/gidden_agent-based_2015.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/62GAD8YI/1.html:text/html}
}

@article{brown_identification_2016,
	title = {Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle},
	volume = {96},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454916303383},
	doi = {10.1016/j.anucene.2016.05.027},
	abstract = {Dynamic fuel cycle simulation tools are intended to model holistic transient nuclear fuel cycle scenarios. As with all simulation tools, fuel cycle simulators require verification through unit tests, benchmark cases, and integral tests. Model validation is a vital aspect, as well. Although comparative studies have been performed, there is no comprehensive unit test and benchmark library for fuel cycle simulator tools. The objective of this paper is to identify some of the {\textquotedblleft}must test{\textquotedblright} functionalities of a fuel cycle simulator tool within the context of specific problems of interest to the Fuel Cycle Options Campaign within the U.S. Department of Energy{\textquoteright}s Office of Nuclear Energy (DOE-NE). This paper identifies the features needed to cover the range of promising fuel cycle options identified in the DOE-NE Fuel Cycle Evaluation and Screening and categorizes these features to facilitate prioritization. Features are categorized as essential functions, integrating features, and exemplary capabilities. A library of unit tests applicable to each of the essential functions should be developed as future work. An international dialog on the functionalities and standard test methods for fuel cycle simulator tools is encouraged.},
	urldate = {2016-09-23},
	journal = {Annals of Nuclear Energy},
	author = {Brown, Nicholas R. and Carlsen, Brett W. and Dixon, Brent W. and Feng, Bo and Greenberg, Harris R. and Hays, Ross D. and Passerini, Stefano and Todosow, Michael and Worrall, Andrew},
	month = oct,
	year = {2016},
	keywords = {Fuel cycle simulator, Transition analysis, Unit tests},
	pages = {88--95},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/9H5GZ7QA/Brown et al. - 2016 - Identification of fuel cycle simulator functionali.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/NFQC7CXG/S0306454916303383.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/Z6WQH4Q4/S0306454916303383.html:text/html}
}

@inproceedings{alvarez-velarde_analysis_2008,
	address = {Mito, Japan},
	title = {Analysis of {European} fuel cycle transition and equilibrium scenarios with {LWR} and {ADS}},
	url = {https://oecd-nea.org/science/reports/2010/actinide10th-poster-docs/I.pdf},
	urldate = {2016-10-27},
	booktitle = {Proc. 10 th {Information} {Exchange} {Meeting} on {Actinide} and {Fission} {Product} {P}\&{T}},
	author = {{\'A}lvarez-Velarde, F. and Mart{\'i}n-Fuertes, F. and Gonz{\'a}lez-Romero, E. M.},
	year = {2008},
	pages = {978--92},
	file = {[PDF] oecd-nea.org:/Users/khuff/Zotero/storage/EHFUBP8M/{\'A}lvarez-Velarde et al. - Analysis of European fuel cycle transition and equ.pdf:application/pdf}
}

@article{merino_rodriguez_analysis_2014,
	title = {Analysis of advanced {European} nuclear fuel cycle scenarios including transmutation and economic estimates},
	volume = {70},
	url = {http://oa.upm.es/33249/},
	number = {null},
	urldate = {2016-10-27},
	journal = {Annals of Nuclear Energy},
	author = {Merino Rodr{\'i}guez, Iv{\'a}n and {\'A}lvarez-Velarde, Francisco and Mart{\'i}n Fuertes, Francisco},
	year = {2014},
	pages = {240--247},
	file = {[PDF] upm.es:/Users/khuff/Zotero/storage/MCWGAFBC/Merino Rodr{\'i}guez et al. - 2014 - Analysis of advanced European nuclear fuel cycle s.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/KNCZX4BG/33249.html:text/html}
}

@inproceedings{carre_overview_2009,
	address = {Paris, France},
	title = {Overview on the {French} nuclear fuel cycle strategy and transition scenario studies},
	url = {https://www.researchgate.net/profile/Frank_Carre/publication/273751217_Overview_on_the_French_Nuclear_Fuel_Cycle_Strategy_and_Transition_Scenario_Studies/links/55f6ace108ae07629dbae8ea.pdf},
	abstract = {This paper gives an overview on the French nuclear fuel cycle strategy and on the scenario studies performed to
describe the transition from Gen II to Gen IV systems. It also gives a presentation of the R\&D performed in France and in
collaboration with international initiatives on advanced fuel cycle associated with Gen IV systems},
	urldate = {2016-10-27},
	booktitle = {Proceedings of {GLOBAL}},
	author = {Carr{\'e}, Frank and Delbecq, Jean-Marie},
	year = {2009},
	pages = {Paper 9439},
	file = {[PDF] researchgate.net:/Users/khuff/Zotero/storage/93TK25DV/Carr{\'e} and Delbecq - 2009 - Overview on the French nuclear fuel cycle strategy.pdf:application/pdf;[PDF] researchgate.net:/Users/khuff/Zotero/storage/A2XM22QS/Carr{\'e} and Delbecq - 2009 - Overview on the French nuclear fuel cycle strategy.pdf:application/pdf}
}

@techreport{boucher_benchmark_2012,
	title = {Benchmark {Study} on {Nuclear} {Fuel} {Cycle} {Transition} {Scenarios} {Analysis} {Codes}},
	number = {NEA/NSC/WPFC/DOC(2012)16},
	institution = {OECD, Nuclear Energy Agency},
	author = {Boucher, L.},
	month = jun,
	year = {2012},
	file = {nsc-wpfc-doc2012-16.pdf:/Users/khuff/Zotero/storage/3SSZVRG4/nsc-wpfc-doc2012-16.pdf:application/pdf}
}

@inproceedings{coquelet-pascal_comparison_2011,
	address = {Makuhari, Japan},
	title = {Comparison of {Different} {Scenarios} for the {Deployment} of {Fast} {Reactors}  in {France} - {Results} {Obtained} with {COSI}},
	url = {http://inis.iaea.org/Search/search.aspx?orig_q=RN:44008962},
	language = {English},
	booktitle = {Proceedings of {GLobal} 2011},
	author = {Coquelet-Pascal, C. and Meyer, M. and Girieud, R. and Eschbach, R. and Chabert, C. and Garzenne, C. and Barbrault, P. and Van Den Durpel, Luc and Duquesnoy, T. and Caron-Charles, M. and Carlier, B. and Lefevre, J. C.},
	month = dec,
	year = {2011},
	file = {GLOBAL2011_Paper501622_Scenarios.pdf:/Users/khuff/Zotero/storage/U3PK445B/GLOBAL2011_Paper501622_Scenarios.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/USKER87I/search.html:text/html}
}

@article{gidden_methodology_2016,
	title = {A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation},
	volume = {310},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549316304101},
	doi = {10.1016/j.nucengdes.2016.10.029},
	abstract = {Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply{\textendash}demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.},
	urldate = {2017-02-08},
	journal = {Nuclear Engineering and Design},
	author = {Gidden, Matthew J. and Wilson, Paul P. H.},
	month = dec,
	year = {2016},
	keywords = {Nuclear Fuel Cycle, Optimization, Agent-based modeling},
	pages = {378--394},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/PNNCUS7D/Gidden and Wilson - 2016 - A methodology for determining the dynamic exchange.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/M6JU4893/S0029549316304101.html:text/html}
}

@article{martin_symbiotic_2017,
	title = {Symbiotic equilibrium between {Sodium} {Fast} {Reactors} and {Pressurized} {Water} {Reactors} supplied with {MOX} fuel},
	volume = {103},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454916308076},
	doi = {10.1016/j.anucene.2017.01.041},
	abstract = {The symbiotic equilibrium between 1.51 GWe breeder SFR (Sodium Fast Reactors) and 1.6 GWe EPR{\texttrademark} (European Pressurized water Reactors) is studied. EPR{\texttrademark} are only supplied with MOX (Mixed OXide) fuel to avoid the use of natural uranium. The equilibrium is studied by considering the flows of plutonium. Its isotopic composition is here described by a single real number referred to as the Pu grade. Plutonium flows through both reactor types are characterized by using linear functions of the Pu grade in new fuels. These functions have been determined by fitting data from a former scenario study carried out with the COSI6 simulation software.
Two different reprocessing strategies are considered. With joint reprocessing of all spent fuels, total and fissile plutonium flows balance for a unique fraction x of EPR{\texttrademark} in the fleet, equal to 0.2547. This x value is consistent with the results reported in the former scenario study mentioned above. When EPR{\texttrademark} spent fuels are used in priority to supply SFR (distinct reprocessing), x reaches 0.2582 at most. COSI6 simulations have been performed to further assess these results. The EPR{\texttrademark} fraction in the fleet at symbiotic equilibrium barely depends on the applied reprocessing strategy, so that the more flexible joint reprocessing constitutes the reference option in that case.},
	urldate = {2017-02-16},
	journal = {Annals of Nuclear Energy},
	author = {Martin, G. and Coquelet-Pascal, C.},
	month = may,
	year = {2017},
	keywords = {Nuclear energy, Plutonium, SFR, Symbiotic nuclear systems, Fuel reprocessing, EPR{\texttrademark}, Thermal reactors, fast reactors},
	pages = {356--362},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/4D8VC2KI/Martin and Coquelet-Pascal - 2017 - Symbiotic equilibrium between Sodium Fast Reactors.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/VPCQBPZW/S0306454916308076.html:text/html}
}

@article{freynet_multiobjective_2016,
	title = {Multiobjective optimization for nuclear fleet evolution scenarios using {COSI}},
	volume = {2},
	url = {http://epjn.epj.org/articles/epjn/abs/2016/01/epjn150066/epjn150066.html},
	urldate = {2017-02-17},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Freynet, David and Coquelet-Pascal, Christine and Eschbach, Romain and Krivtchik, Guillaume and Merle-Lucotte, Elsa},
	year = {2016},
	pages = {9},
	file = {[HTML] epj-n.org:/Users/khuff/Zotero/storage/AVP329PE/epjn150066.html:text/html;[HTML] epj-n.org:/Users/khuff/Zotero/storage/ZHNXV2WH/epjn150066.html:text/html;epjn150066.pdf:/Users/khuff/Zotero/storage/HA6HH8VJ/epjn150066.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/HIBGZJTC/epjn150066.html:text/html;Snapshot:/Users/khuff/Zotero/storage/8URTHTBQ/epjn150066.html:text/html}
}

@article{wigeland_nuclear_2014,
	title = {Nuclear {Fuel} {Cycle} {Evaluation} and {Screening} - {Final} {Report}},
	url = {https://fuelcycleevaluation.inl.gov/Shared%20Documents/ES%20Main%20Report.pdf},
	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},
	file = {ES Main Report.pdf:/Users/khuff/Zotero/storage/WEVPB9EQ/ES Main Report.pdf:application/pdf}
}

@techreport{oecd_spent_2011,
	title = {Spent {Nuclear} {Fuel} {Asssay} {Data} for {Isotopic} {Validation}},
	url = {https://www.oecd-nea.org/science/wpncs/ADSNF/SOAR_final.pdf},
	abstract = {Management of spent fuel from commercial nuclear reactors is a key issue for many NEA
member countries. As interim storage facilities in many countries reach their design capacities,
the need to optimise spent fuel storage management is becoming an increasingly important
issue to managing fuel cycle costs while reducing associated risks. In nuclear criticality safety
studies involving spent fuel, burn-up credit is being pursued and has been implemented in many
countries as a means of more accurately and realistically determining the system reactivity by
taking into account a decrease in the reactivity of spent fuel during irradiation. Implementation
of burn-up credit has gained in world-wide interest during the last 20 years and it represents one
of the most technically challenging issues in nuclear criticality safety. To address these challenges
and help co-ordinate activities in NEA member countries, the Working Party on Nuclear
Criticality Safety (WPNCS) of the OECD/NEA Nuclear Science Committee (NSC) has organised the
Expert Group on Burn-up Credit Criticality (EGBUC). The decision of many countries to advance
burn-up credit as part of their criticality safety licensing strategy has heightened interest in
measurement data needed to validate code calculations for a burn-up credit methodology.},
	institution = {Nuclear Energy Agency},
	author = {OECD},
	year = {2011}
}

@techreport{hermann_validation_1995,
	title = {Validation of the {SCALE} system for {PWR} spent fuel isotopic composition analyses},
	url = {http://www.osti.gov/scitech/biblio/57886},
	urldate = {2017-04-03},
	institution = {Oak Ridge National Lab., TN (United States)},
	author = {Hermann, O. W. and Bowman, S. M. and Parks, C. V. and Brady, M. C.},
	year = {1995}
}

@techreport{iaea_management_2007,
	address = {Vienna, Austria},
	type = {{TECDOC}},
	title = {Management iof {Reprocessed} {Uraniuim}},
	url = {http://www-pub.iaea.org/MTCD/publications/PDF/te_1529_web.pdf},
	abstract = {The International Atomic Energy Agency is giving continuous attention to the collection,
analysis and exchange of information on issues of back-end of the nuclear fuel cycle, an
important part of the nuclear fuel cycle. Reprocessing of spent fuel arising from nuclear
power production is one of the strategies for the back end of the fuel cycle. As a major
fraction of spent fuel is made up of uranium, chemical reprocessing of spent fuel would leave
behind large quantities of separated uranium which is designated as reprocessed uranium
(RepU). Reprocessing of spent fuel could form a crucial part of future fuel cycle
methodologies, which currently aim to separate and recover plutonium and minor actinides.
The use of reprocessed uranium (RepU) and plutonium reduces the overall environmental
impact of the entire fuel cycle. Environmental considerations will be important in determining
the future growth of nuclear energy. It should be emphasized that the recycling of fissile
materials not only reduces the toxicity and volumes of waste from the back end of the fuel
cycle; it also reduces requirements for fresh milling and mill tailings. In comparison, the
method of direct disposal of spent fuel premeditates creation of larger capacity repositories for
permanent disposal. The issue of recycle and reuse of valuable material is important for the
nuclear fuel cycle in the context of sustainable growth of the nuclear energy. Recognizing the
importance of this subject, the International Atomic Energy Agency initiated the preparation
of this report to review and summarize information available on the management of
reprocessed uranium.},
	language = {English},
	number = {1529},
	urldate = {2017-04-28},
	institution = {IAEA},
	author = {IAEA},
	month = feb,
	year = {2007},
	pages = {108}
}

@misc{world_nuclear_association_nuclear_2017,
	title = {Nuclear {Power} in the {European} {Union} - {World} {Nuclear} {Association}},
	url = {http://www.world-nuclear.org/information-library/country-profiles/others/european-union.aspx},
	urldate = {2017-04-17},
	author = {World Nuclear Association},
	month = feb,
	year = {2017},
	file = {Nuclear Power in the European Union - World Nuclear Association:/Users/khuff/Zotero/storage/VG9QDBRU/european-union.html:text/html}
}

@techreport{schneider_spent_2008,
	type = {Research {Report}},
	title = {Spent nuclear fuel reprocessing in {France}},
	url = {http://www.psr.org/nuclear-bailout/resources/spent-nuclear-fuel.pdf},
	number = {4},
	institution = {International Panel on Fissile Materials},
	author = {Schneider, Mycle and Marignac, Yves},
	month = apr,
	year = {2008},
	note = {http://fissilematerials.org/library/rr04.pdf}
}

@inproceedings{hugelmann_melox_1999,
	title = {{MELOX} fuel fabrication plant: operational feedback and future prospects},
	volume = {3},
	shorttitle = {{MELOX} fuel fabrication plant},
	url = {http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/31/062/31062323.pdf#page=110},
	urldate = {2017-05-03},
	booktitle = {{MOX} {Fuel} {Cycle} {Technologies} for {Medium} and {Long} {Term} {Deployment} ({Proc}. {Symp}. {Vienna}, 1999), {C}\&{S} {Papers} {Series} {No}},
	author = {Hugelmann, D. and Greneche, D.},
	year = {1999},
	pages = {102--108},
	file = {[PDF] iaea.org:/Users/khuff/Zotero/storage/II69N986/Hugelmann and Greneche - 1999 - MELOX fuel fabrication plant operational feedback.pdf:application/pdf}
}

@article{lamarsh_introduction_1983,
	title = {Introduction to nuclear engineering},
	url = {https://inis.iaea.org/search/search.aspx?orig_q=RN:17073185},
	urldate = {2017-05-11},
	author = {Lamarsh, John R.},
	year = {1983},
	file = {Snapshot:/Users/khuff/Zotero/storage/SZH27EZ6/search.html:text/html}
}

@book{hatch_politics_2015,
	title = {Politics and {Nuclear} {Power}: {Energy} {Policy} in {Western} {Europe}},
	isbn = {978-0-8131-6307-9},
	shorttitle = {Politics and {Nuclear} {Power}},
	abstract = {With the dramatic changes OPEC precipitated in the structure of world energy markets during the 1970s, energy became a central concern to policymakers throughout the industrialized West. This book ex-amines the responses of public officials in three leading European nations -- the Federal Republic of Germany, France, and the Netherlands -- to the energy crisis. As the study shows, the proposed energy programs in the three countries shared remarkable similarities; yet the policy outcomes were very different. To explain why, Michael T. Hatch goes beyond the specific content of government energy policy to include an analysis of the policymaking process itself.At the heart of the study is an exploration of the various dimensions of nuclear policy in West Germany. The political consensus on nuclear power that prevailed in the initial years following the energy crisis disintegrated as antinuclear "citizens' initiatives," the courts, and trade unions, as well as the traditional political parties, entered the policymaking process. Subsequent government efforts to resolve the political stalemate over nuclear power foundered in a morass of domestic electoral politics and an international debate over nuclear proliferation.Extending the analysis to comparisons with French and Dutch nuclear strategies, Hatch argues that the critical factor in determining nuclear policy was the manner in which the political system structured the nuclear debate. In contrast to West Germany, where the electoral and parliamentary systems enhanced the influence of the antinuclear "Greens," the electoral system and constellation of political parties in France served to dissipate the influence of the antinuclear forces. Thus in France the nuclear program en-countered few impediments. In the Netherlands, as in West Germany, government policy was paralyzed in the face of antinuclear sentiment across a broad spectrum of Dutch society.Hatch has provided here not only a useful examination of the development of energy policy in western Europe but also a case study of the close interplay between policy and politics.},
	language = {en},
	publisher = {University Press of Kentucky},
	author = {Hatch, Michael T.},
	month = jan,
	year = {2015},
	note = {Google-Books-ID: TrwfBgAAQBAJ},
	keywords = {History / Europe / Western, Political Science / Public Policy / Science \& Technology Policy, Technology \& Engineering / Power Resources / Nuclear}
}

@techreport{joskow_future_2012,
	type = {Working {Paper}},
	title = {The {Future} of {Nuclear} {Power} {After} {Fukushima}},
	copyright = {An error occurred getting the license - uri.},
	url = {http://dspace.mit.edu/handle/1721.1/70857},
	abstract = {This paper analyzes the impact of the Fukushima accident on the future of nuclear
power around the world. We begin with a discussion of the {\textquoteleft}but for{\textquoteright} baseline and the
much discussed {\textquoteleft}nuclear renaissance.{\textquoteright} Our pre-Fukushima benchmark for growth in
nuclear generation in the U.S. and other developed countries is much more modest than
many bullish forecasts of a big renaissance in new capacity may have suggested. For at
least the next decade in developed countries, it is composed primarily of life extensions
for many existing reactors, modest uprates of existing reactors as their licenses are
extended, and modest levels of new construction. The majority of forecasted new
construction is centered in China, Russia and the former states of the FSU, India and
South Korea. In analyzing the impact of Fukushima, we break the effect down into two
categories: the impact on existing plants, and the impact on the construction of new units.
In both cases, we argue that the accident at Fukushima will contribute to a reduction in
future trends in the expansion of nuclear energy, but at this time these effects appear to be
quite modest at the global level.},
	language = {en\_US},
	urldate = {2017-05-17},
	institution = {MIT CEEPR},
	author = {Joskow, Paul L. and Parsons, John E.},
	month = feb,
	year = {2012},
	file = {Full Text PDF:/Users/khuff/Zotero/storage/29IIH4F6/Joskow and Parsons - 2012 - The Future of Nuclear Power After Fukushima.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/DW6XA46Q/70857.html:text/html}
}

@inproceedings{varaine_pre-conceptual_2012,
	address = {Chicago, IL},
	title = {Pre-conceptual design study of {ASTRID} core},
	url = {https://www.osti.gov/scitech/biblio/22105982},
	abstract = {In the framework of the ASTRID project at CEA, core design studies are performed at CEA with the AREVA and EDF support. At the stage of the project, pre-conceptual design studies are conducted in accordance with GEN IV reactors criteria, in particularly for safety improvements. An improved safety for a sodium cooled reactor requires revisiting many aspects of the design and is a rather lengthy process in current design approach. Two types of cores are under evaluation, one classical derivated from the SFR V2B and one more challenging called CFV (low void effect core) with a large gain on the sodium void effect. The SFR V2b core have the following specifications : a very low burn-up reactivity swing (due to a small cycle reactivity loss) and a reduced sodium void effect with regard to past designs such as the EFR (around 2\$ minus). Its performances are an average burn-up of 100 GWd/t, and an internal conversion ratio equal to one given a very good behavior of this core during a control rod withdrawal transient). The CFV with its specific design offers a negative sodium void worth while maintaining core performances. In accordance of ASTRID needs for demonstration those cores are 1500 MWth power (600 MWe). This paper will focus on the CFV pre-conceptual design of the core and S/A, and the performances in terms of safety will be evaluated on different transient scenario like ULOF, in order to assess its intrinsic behavior compared to a more classical design like V2B core. The gap in term of margin to a severe accident due to a loss of flow initiator underlines the potential capability of this type of core to enhance prevention of severe accident in accordance to safety demonstration. 

Pre-conceptual design study of ASTRID core (PDF Download Available). Available from: https://www.researchgate.net/publication/282657288\_Pre-conceptual\_design\_study\_of\_ASTRID\_core [accessed Aug 31, 2017].},
	language = {English},
	urldate = {2017-05-19},
	booktitle = {Proceedings of {ICAPP} 2012},
	publisher = {American Nuclear Society - ANS},
	author = {Varaine, F. and Marsault, P. and Chenaud, M. S. and Bernardin, B. and Conti, A. and Sciora, P. and Venard, C. and Fontaine, B. and Devictor, N. and Martin, L. and Scholer, A. C. and Verrier, D.},
	month = jul,
	year = {2012},
	note = {OSTI: 22105982},
	pages = {Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24--28 Jun 2012; Other Information: Country of input: France; 10 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants -- ICAPP '12{\textbar} 2799 p.},
	file = {[PDF] researchgate.net:/Users/khuff/Zotero/storage/2B4SNXP4/MARSAULT{\textendash}Marie-Sophie et al. - Pre-conceptual design study of ASTRID core.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/GIVT87ET/22105982.html:text/html}
}

@article{sutharshan_ap1000tm_2011,
	series = {Asian {Nuclear} {Prospects} 2010},
	title = {The {AP}1000TM {Reactor}: {Passive} {Safety} and {Modular} {Design}},
	volume = {7},
	issn = {1876-6102},
	shorttitle = {The {AP}1000TM {Reactor}},
	url = {http://www.sciencedirect.com/science/article/pii/S1876610211015475},
	doi = {10.1016/j.egypro.2011.06.038},
	abstract = {Our world is ever growing, there will be higher demands on electricity, and fossil fuels cannot satisfy this demand without further harming the environment. Likewise, renewable energy sources such as solar and winds are still in their infancy and, when used alone, are not realistic solutions to meet this demand. Westinghouse Electric Company is ready to address higher electricity demand with the only Generation III+reactor to receive Design Certification from the United States Nuclear Regulatory Commission, the AP1000{\texttrademark} pressurized water reactor (PWR). Westinghouse Electric Company once again sets a new industry standard with the AP1000{\texttrademark} reactor. The AP1000{\texttrademark} is a two-loopPressurized Water Reactor (PWR) with passive safety features and extensive plant simplifications that enhance its construction, operation, maintenance and safety. The paper discusses the unique design features of AP 1000.},
	urldate = {2017-05-12},
	journal = {Energy Procedia},
	author = {Sutharshan, Balendra and Mutyala, Meena and Vijuk, Ronald P and Mishra, Alok},
	month = jan,
	year = {2011},
	keywords = {Generation III+ reactor, core operating parameters, modular design, passive safety, probabilistic risk assessment, PWR},
	pages = {293--302},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/2D66N8K4/Sutharshan et al. - 2011 - The AP1000TM Reactor Passive Safety and Modular D.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/E87IC8RM/S1876610211015475.html:text/html}
}

@techreport{cne2_reports_2015,
	title = {Reports of the {CNE}2},
	url = {https://www.cne2.fr/index.php/en/cne-2-2007-to-this-day},
	abstract = {According to the provisions of the 2006 act, the long-term management of high and intermediatelevel
waste involves two related components: the partitioning-transmutation of actinides found in the
spent fuel of future nuclear reactors and the geological disposal of long-lived high and intermediatelevel
waste (LLHLW \& LLILW) in accordance with the principle of reversibility. In addition, facilities
in the front-end and back-end of the nuclear fuel cycle and the dismantling of decommissioned
facilities produce long-lived low-level waste (LLLLW), very low-level waste (VLLW) and waste
with augmented natural radioactivity. The LLLLW pose different management problems due to the
very large quantities produced. Short-lived low and intermediate-level waste is stored at the Aube
storage centre (centre de stockage de l{\textquoteright}Aube {\textendash} CSA)},
	language = {English},
	urldate = {2017-06-24},
	institution = {Commission Nationae D'Evaluation},
	author = {CNE2},
	month = jun,
	year = {2015},
	pages = {120},
	file = {CNE2 - Reports of the CNE2 - 2007 to this day:/Users/khuff/Zotero/storage/9WF2G3QN/cne-2-2007-to-this-day.html:text/html}
}

@article{salvatores_nuclear_2005,
	title = {Nuclear fuel cycle strategies including {Partitioning} and {Transmutation}},
	volume = {235},
	issn = {0029-5493},
	url = {http://www.sciencedirect.com/science/article/pii/S0029549304003759},
	doi = {10.1016/j.nucengdes.2004.10.009},
	abstract = {The widespread concern about radioactive waste management has promoted interest during the last decade for the potential role of Partitioning and Transmutation strategies, in order to alleviate the burden on future deep geological repositories. The physics of transmutation allows to point-out preferential approaches, e.g., based on the use of a fast neutron spectrum. The practical implementation of Partitioning and Transmutation implies the development of sophisticated technologies and can be more realistic if seen in a regional context. Some examples will be given to illustrate the {\textquotedblleft}regional{\textquotedblright} approach, and some considerations will be made on the use of Accelerator Driven Systems (ADS), in the frame of a progressive strategy from present nuclear power fleets to future systems, as studied, e.g., in the frame of the GENERATION-IV initiative.},
	number = {7},
	journal = {Nuclear Engineering and Design},
	author = {Salvatores, M.},
	month = mar,
	year = {2005},
	pages = {805--816},
	file = {Fulltext:/Users/khuff/Zotero/storage/K54ZFPU4/S0029549304003759.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/3PMMTCTG/S0029549304003759.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/T4QF2IF2/S0029549304003759.html:text/html;Snapshot:/Users/khuff/Zotero/storage/7D7YTFSV/S0029549304003759.html:text/html}
}

@misc{fazio_study_2013,
	title = {Study on partitioning and transmutation as a possible option for spent fuel management within a nuclear phase out scenario},
	url = {https://www.researchgate.net/publication/264479296_Study_on_partitioning_and_transmutation_as_a_possible_option_for_spent_fuel_management_within_a_nuclear_phase_out_scenario},
	abstract = {Most Partitioning and Transmutation (P\&T) studies
implicitly presuppose the continuous use of nuclear
energy [1]. In this case the development of new facilities
or the modification of the fuel cycle can be justified in the
long-term as an important feature in order to improve
sustainability by minimizing radioactive waste and
reducing the burden at waste disposal.
In the case of a country with nuclear energy phase-out
policy, the P\&T option might have also an important role
for what concerns the final disposal strategies of the spent
fuel. In this work three selected scenarios are analyzed in
order to assess the impact of P\&T implementation in a
nuclear energy phase out option.},
	urldate = {2017-06-27},
	journal = {ResearchGate},
	author = {Fazio, C},
	month = oct,
	year = {2013},
	file = {Snapshot:/Users/khuff/Zotero/storage/2STTNZDS/264479296_Study_on_partitioning_and_transmutation_as_a_possible_option_for_spent_fuel_management.pdf:application/pdf}
}

@article{madic_futuristic_2007,
	series = {Proceedings of the {Plutonium} {Futures} - {The} {Science} 2006 {Conference}},
	title = {Futuristic back-end of the nuclear fuel cycle with the partitioning of minor actinides},
	volume = {444},
	issn = {0925-8388},
	url = {http://www.sciencedirect.com/science/article/pii/S0925838807012029},
	doi = {10.1016/j.jallcom.2007.05.051},
	abstract = {For future back-end of the nuclear fuel cycle, the partitioning of minor actinides: Np, Am and Cm, followed by their transmutation will minimize importantly the radiotoxicity of nuclear glass waste. In this paper, the research done in France and in Europe will be presented: (i) partitioning of Np by modified PUREX process, (ii) partitioning of Am and Cm by the DIAMEX and SANEX hydrometallurgical processes.},
	journal = {Journal of Alloys and Compounds},
	author = {Madic, C. and Boullis, B. and Baron, P. and Testard, F. and Hudson, M. J. and Liljenzin, J. -O. and Christiansen, B. and Ferrando, M. and Facchini, A. and Geist, A. and Modolo, G. and Espartero, A. G. and De Mendoza, J.},
	month = oct,
	year = {2007},
	keywords = {Actinide alloys and compounds},
	pages = {23--27},
	file = {ScienceDirect Snapshot:/Users/khuff/Zotero/storage/QNKQI4NX/S0925838807012029.html:text/html}
}

@article{martinez-val_pateros_2009,
	title = {{PATEROS} {P}\&{T} {Roadmap} proposal for advanced fuel cycles leading to a sustainable nuclear energy: syntheses report},
	shorttitle = {{PATEROS} {P}\&{T} {Roadmap} proposal for advanced fuel cycles leading to a sustainable nuclear energy},
	author = {Martinez-Val, J.},
	year = {2009}
}

@techreport{piet_implications_2010,
	title = {Implications of {Fast} {Reactor} {Transuranic} {Conversion} {Ratio}},
	url = {https://www.researchgate.net/profile/Steve_Piet/publication/255218036_Implications_of_Fast_Reactor_Transuranic_Conversion_Ratio/links/54f87b470cf2ccffe9df3b55/Implications-of-Fast-Reactor-Transuranic-Conversion-Ratio.pdf},
	institution = {Idaho National Laboratory (INL)},
	author = {Piet, Steven J. and Hoffman, Edward A. and Bays, Samuel E.},
	year = {2010},
	file = {[PDF] researchgate.net:/Users/khuff/Zotero/storage/WSSD6JHQ/Piet et al. - 2010 - Implications of Fast Reactor Transuranic Conversio.pdf:application/pdf}
}

@phdthesis{fabbris_optimisation_2014,
	type = {phdthesis},
	title = {Optimisation multi-physique et multi-crit{\`e}re des coeurs de {RNR}-{Na} : application au concept {CFV}},
	shorttitle = {Optimisation multi-physique et multi-crit{\`e}re des coeurs de {RNR}-{Na}},
	url = {https://tel.archives-ouvertes.fr/tel-01133491/document},
	abstract = {La conception du coeur d{\textquoteright}un r{\'e}acteur nucl{\'e}aire est fortement multidisciplinaire (neutronique, thermo-hydraulique, thermom{\'e}canique du combustible, physique du cycle, etc.). Le probl{\`e}me est aussi de type multi-objectif (plusieurs performances) {\`a} grand nombre de dimensions (plusieurs dizaines de param{\`e}tres de conception).Les codes de calculs d{\'e}terministes utilis{\'e}s traditionnellement pour la caract{\'e}risation des coeurs demandant d{\textquoteright}importantes ressources informatiques, l{\textquoteright}approche de conception classique rend difficile l{\textquoteright}exploration et l{\textquoteright}optimisation de nouveaux concepts innovants. Afin de pallier ces difficult{\'e}s, une nouvelle m{\'e}thodologie a {\'e}t{\'e} d{\'e}velopp{\'e}e lors de ces travaux de th{\`e}se. Ces travaux sont bas{\'e}s sur la mise en oeuvre et la validation de sch{\'e}mas de calculs neutronique et thermo-hydraulique pour disposer d{\textquoteright}un outil de caract{\'e}risation d{\textquoteright}un coeur de r{\'e}acteur {\`a} neutrons rapides {\`a} caloporteur sodium tant du point de vue des performances neutroniques que de son comportement en transitoires accidentels.La m{\'e}thodologie mise en oeuvre s{\textquoteright}appuie sur la construction de mod{\`e}les de substitution (ou m{\'e}tamod{\`e}les) aptes {\`a} remplacer la cha{\^i}ne de calcul neutronique et thermo-hydraulique. Des m{\'e}thodes math{\'e}matiques avanc{\'e}es pour la planification d{\textquoteright}exp{\'e}riences, la construction et la validation des m{\'e}tamod{\`e}les permettent de remplacer cette cha{\^i}ne de calcul par des mod{\`e}les de r{\'e}gression au pouvoir de pr{\'e}diction {\'e}lev{\'e}.La m{\'e}thode est appliqu{\'e}e {\`a} un concept innovant de coeur {\`a} Faible coefficient de Vidange sur un tr{\`e}s large domaine d{\textquoteright}{\'e}tude, et {\`a} son comportement lors de transitoires thermo-hydrauliques non prot{\'e}g{\'e}s pouvant amener {\`a} des situations incidentelles, voire accidentelles. Des analyses globales de sensibilit{\'e} permettent d{\textquoteright}identifier les param{\`e}tres de conception influents sur la conception du coeur et son comportement en transitoire. Des optimisations multicrit{\`e}res conduisent {\`a} des nouvelles configurations dont les performances sont parfois significativement am{\'e}lior{\'e}es. La validation des r{\'e}sultats produits au cours de ces travaux de th{\`e}se d{\'e}montre la pertinence de la m{\'e}thode au stade de la pr{\'e}conception d{\textquoteright}un coeur de r{\'e}acteur {\`a} neutrons rapides refroidi au sodium.},
	language = {fr},
	urldate = {2017-07-21},
	school = {Universit{\'e} de Grenoble},
	author = {Fabbris, Olivier},
	month = oct,
	year = {2014},
	file = {Full Text PDF:/Users/khuff/Zotero/storage/AI9FANBF/Fabbris - 2014 - Optimisation multi-physique et multi-crit{\`e}re des c.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/54B5PP4P/tel-01133491.html:text/html}
}

@article{gabrielli_astrid-like_2015,
	series = {The {Fourth} {International} {Symposium} on {Innovative} {Nuclear} {Energy} {Systems}, {INES}-4},
	title = {{ASTRID}-like {Fast} {Reactor} {Cores} for {Burning} {Plutonium} and {Minor} {Actinides}},
	volume = {71},
	issn = {1876-6102},
	url = {http://www.sciencedirect.com/science/article/pii/S1876610214026927},
	doi = {10.1016/j.egypro.2014.11.863},
	abstract = {A reduction of nuclear waste by transmutation of trans-uranium elements (TRUs), such as Pu and Minor Actinides (MAs) contained in Spent Nuclear Fuel (SNF), is a goal for future reactors. In general, countries with on-going nuclear scenarios would profit from MA mass stabilization, while transmutation of Pu and MAs from SNF could be desired in countries in nuclear phase-out. Both missions can be accomplished by employing fast reactors loaded with fuels containing different amounts of Pu and MAs in a closed (or partially closed) fuel cycle. In this paper, two 1200 MWth sodium-cooled fast reactor cores, based on the French ASTRID design, are proposed for burning TRUs (phase-out option) or only MAs (on-going option). Main attention is focused on the safety and on the transmutation performance. The coolant void effect, in the region including the core and the plenum above and the Doppler constant of both systems are negative also with irradiated fuel. The conversion ratios (CR) of the Pu and MA burners are in the ranges from 0.6 to 0.7 and from 0.5 to 0.6, respectively. These results show a large safety and transmutation potential of ASTRID type reactors.},
	journal = {Energy Procedia},
	author = {Gabrielli, Fabrizio and Rineiski, Andrei and Vezzoni, Barbara and Maschek, Werner and Fazio, Concetta and Salvatores, Massimo},
	month = may,
	year = {2015},
	keywords = {Nuclear Fuel Cycle, Transmutation, Nuclear reactor safety, Sodium fast reactors},
	pages = {130--139},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/2APV2MPJ/Gabrielli et al. - 2015 - ASTRID-like Fast Reactor Cores for Burning Plutoni.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/I78CKW34/S1876610214026927.html:text/html}
}

@book{iaea_nuclear_2017,
	address = {Vienna, Austria},
	series = {Reference {Data} {Series}},
	title = {Nuclear {Power} {Reactors} in the {World}},
	url = {http://www-pub.iaea.org/books/IAEABooks/12237/Nuclear-Power-Reactors-in-the-World},
	abstract = {Nuclear Power Reactors in the World 2017 Edition},
	language = {English},
	number = {2},
	urldate = {2017-09-10},
	publisher = {IAEA},
	author = {IAEA, PRIS},
	year = {2017},
	file = {Full Text PDF:/Users/khuff/Zotero/storage/XRPA6LRK/IAEA - 2017 - Nuclear Power Reactors in the World.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/N7TTNBDG/Nuclear-Power-Reactors-in-the-World-2017-Edition.html:text/html}
}

@inproceedings{gidden_agent-based_2015-1,
	address = {Kyoto, Japan},
	title = {Agent-based dynamic resource exchange in {CYCLUS}},
	url = {http://inis.iaea.org/Search/search.aspx?orig_q=RN:47042686},
	doi = {10.11484/jaea-conf-2014-003},
	abstract = {A novel methodology for modeling the dynamic exchange of resources among actors in the CYCLUS fuel cycle simulator is described. The methodology is comprised of an information gathering step, a bipartite-graph-based supply-demand matching step, and a trade execution step. Its implementation in CYCLUS allows the simulator to model generic fuel cycles, i.e., those in which the types of facilities and possible resource flows is not known a priori. The flow of resources at each time step is algorithmically determined based on facilities{\textquoteright} resource flow preferences. The dynamicsim of both the preference-based flows and quantity and quality constraints on those flows are demonstrated via two simple scenarios. The first scenario exemplifies situations in which actors{\textquoteright} preferences change over time and the second typifies situations in which quality-based constraints limit resource flow. This generic capability provides a sufficient framework and basis for the CYCLUS simulation engine to model complex, advanced fuel cycles. (author)},
	language = {English},
	urldate = {2017-09-14},
	publisher = {JAEA},
	author = {Gidden, Matthew and Carlsen, Robert and Opotowsky, Arrielle and Rakhimov, Olzhas and Scopatz, Anthony M. and Wilson, Paul P. H.},
	year = {2015},
	file = {Snapshot:/Users/khuff/Zotero/storage/4VK7Z6KI/search.html:text/html}
}

@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{hinds_next-generation_2006,
	title = {Next-generation nuclear energy: {The} {ESBWR}},
	volume = {49},
	shorttitle = {Next-generation nuclear energy},
	number = {1},
	journal = {Nuclear News},
	author = {Hinds, David and Maslak, Chris},
	year = {2006},
	pages = {35--40},
	file = {Fulltext:/Users/khuff/Zotero/storage/UNWZKM5B/Hinds and Maslak - 2006 - Next-generation nuclear energy The ESBWR.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/8F69B8G6/Hinds and Maslak - 2006 - Next-generation nuclear energy The ESBWR.pdf:application/pdf}
}

@techreport{parks_overview_1992,
	title = {Overview of {ORIGEN}2 and {ORIGEN}-{S}: {Capabilities} and limitations},
	shorttitle = {Overview of {ORIGEN}2 and {ORIGEN}-{S}},
	url = {https://www.osti.gov/biblio/10116143},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {English},
	number = {CONF-920430-47},
	urldate = {2018-02-22},
	institution = {Oak Ridge National Lab., TN (United States)},
	author = {Parks, C. V.},
	month = feb,
	year = {1992},
	file = {Fulltext:/Users/khuff/Zotero/storage/K4A7U3YJ/Parks - 1992 - Overview of ORIGEN2 and ORIGEN-S Capabilities and.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/9KK2732Z/10116143.html:text/html;Snapshot:/Users/khuff/Zotero/storage/44XC8RDD/search.html:text/html}
}

@article{zhao_improving_2009,
	title = {Improving {SFR} economics through innovations from thermal design and analysis aspects},
	volume = {239},
	issn = {0029-5493},
	url = {http://www.sciencedirect.com/science/article/pii/S0029549309000892},
	doi = {10.1016/j.nucengdes.2009.02.012},
	abstract = {Achieving economic competitiveness as compared to LWRs and other Generation IV (Gen-IV) reactors is one of the major requirements to attract large-scale investment in commercial sodium cooled fast reactor (SFR) power plants. Advances in R\&D for advanced SFR fuel and structural materials provide key long-term opportunities to improve SFR economics. In addition, other new opportunities are emerging to further improve SFR economics. This paper provides an overview on potential ideas from the perspective of thermal hydraulics to improve SFR economics. These include: (1) a new hybrid loop-pool reactor design to further optimize economics, safety, and reliability of SFRs with more flexibility, (2) a multiple-reheat and intercooling helium Brayton cycle to improve plant thermal efficiency and to reduce safety related overnight and operation costs, and (3) modern multi-physics thermal analysis methods to reduce analysis uncertainties and associated requirements for over-conservatism in reactor design. This paper reviews advances in all three areas and their potential beneficial impacts on SFR economics.},
	number = {6},
	urldate = {2018-02-22},
	journal = {Nuclear Engineering and Design},
	author = {Zhao, Haihua and Zhang, Hongbin and Mousseau, Vincent A. and Peterson, Per F.},
	month = jun,
	year = {2009},
	pages = {1042--1055},
	file = {ScienceDirect Snapshot:/Users/khuff/Zotero/storage/YM53G9K2/S0029549309000892.html:text/html}
}

@article{topfer_germanys_2011,
	title = {Germany{\textquoteright}s {Energy} {Turnaround}{\textendash}{A} {Collective} {Effort} for the {Future}},
	journal = {Ethics Commission for a Safe Energy Supply. On behalf of Federal Chancellor Dr. Angela Merkel},
	author = {T{\"o}pfer, K. and Kleiner, M. and Beck, U. and Fisher, U. and van Donhanyi, K. and Gluck, A. and Hacker, J. and Hambrecht, J. and Hauff, V. and Hirche, W.},
	year = {2011}
}

@techreport{croff_origen2:_1980,
	title = {{ORIGEN}2: a revised and updated version of the {Oak} ridge isotope generation and depletion code},
	shorttitle = {{ORIGEN}2},
	institution = {Oak Ridge National Lab., TN (USA)},
	author = {Croff, A. G.},
	year = {1980},
	file = {Fulltext:/Users/khuff/Zotero/storage/UMFRHNC5/Croff - 1980 - ORIGEN2 a revised and updated version of the Oak .pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/SS4KQ6XZ/5352089.html:text/html}
}

@article{chenaud_status_2013,
	title = {{STATUS} {OF} {THE} {ASTRID} {CORE} {AT} {THE} {END} {OF} {THE} {PRE}-{CONCEPTUAL} {DESIGN} {PHASE} 1},
	volume = {45},
	issn = {1738-5733},
	url = {http://www.sciencedirect.com/science/article/pii/S1738573315301741},
	doi = {10.5516/NET.02.2013.519},
	abstract = {Within the framework of the ASTRID project, core design studies are being conducted by the CEA with support from AREVA and EDF. The pre-conceptual design studies are being conducted in accordance with the GEN IV reactor objectives, particularly in terms of improving safety. This involves limiting the consequences of 1) a hypothetical control rod withdrawal accident (by minimizing the core reactivity loss during the irradiation cycle), and 2) an hypothetical loss-of-flow accident (by reducing the sodium void worth). Two types of cores are being studied for the ASTRID project. The first is based on a {\textquoteleft}large pin/small spacing wire{\textquoteright} concept derived from the SFR V2b, while the other is based on an innovative CFV design. A distinctive feature of the CFV core is its negative sodium void worth. In 2011, the evaluation of a preliminary version (v1) of this CFV core for ASTRID underlined its potential capacity to improve the prevention of severe accidents. An improved version of the ASTRID CFV core (v2) was proposed in 2012 to comply with all the control rod withdrawal criteria, while increasing safety margins for all unprotected-loss-of-flow (ULOF) transients and improving the general design. This paper describes the CFV v2 design options and reports on the progress of the studies at the end of pre-conceptual design phase 1 concerning: {\textendash}Core performance,{\textendash}Intrinsic behavior during unprotected transients,{\textendash}Simulation of severe accident scenarios,{\textendash}Qualification requirements. The paper also specifies the open options for the materials, sub-assemblies, absorbers, and core monitoring that will continue to be studied during the conceptual design phase.},
	number = {6},
	urldate = {2018-10-29},
	journal = {Nuclear Engineering and Technology},
	author = {Chenaud, MS. and Devictor, N. and Mignot, G. and Varaine, F. and V{\'e}nard, C. and Martin, L. and Phelip, M. and Lorenzo, D. and Serre, F. and Bertrand, F. and Alpy, N. and Le flem, M. and Gavoille, P. and Lavastre, R. and Richard, P. and Verrier, D. and Schmitt, D.},
	month = nov,
	year = {2013},
	keywords = {ASTRID Core Design Pre-conceptual Design},
	pages = {721--730},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/I5E6H3RS/Chenaud et al. - 2013 - STATUS OF THE ASTRID CORE AT THE END OF THE PRE-CO.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/7HFQ6PPW/Chenaud et al. - 2013 - STATUS OF THE ASTRID CORE AT THE END OF THE PRE-CO.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/P8644UP7/S1738573315301741.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/PPJWRRPY/S1738573315301741.html:text/html}
}

@article{gauche_generation_2012,
	series = {Science of nuclear safety post-{Fukushima}},
	title = {Generation {IV} reactors and the {ASTRID} prototype: {Lessons} from the {Fukushima} accident},
	volume = {13},
	issn = {1631-0705},
	shorttitle = {Generation {IV} reactors and the {ASTRID} prototype},
	url = {http://www.sciencedirect.com/science/article/pii/S1631070512000369},
	doi = {10.1016/j.crhy.2012.03.004},
	abstract = {In France, the ASTRID prototype is a sodium-cooled fast neutron industrial demonstrator, fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for 3rd generation reactors, and take into account lessons from the Fukushima accident. The objectives are to reinforce the robustness of the safety demonstration for all safety functions. ASTRID will feature an innovative core with a negative sodium void coefficient, take advantage of the large thermal inertia of SFRs for decay heat removal, and provide for a design either eliminating the sodium{\textendash}water reaction, or guaranteeing no consequences for safety in case such reaction would take place.
R{\'e}sum{\'e}
En France, le prototype ASTRID est un d{\'e}monstrateur industriel {\`a} neutrons rapides, refroidi au sodium, r{\'e}pondant aux crit{\`e}res des r{\'e}acteurs de 4{\`e}me g{\'e}n{\'e}ration. ASTRID sera soumis {\`a} des crit{\`e}res de s{\^u}ret{\'e} aussi s{\'e}v{\`e}res que pour les r{\'e}acteurs de 3{\`e}me g{\'e}n{\'e}ration, et prendra en compte les enseignements de l'accident de Fukushima. L'objectif est de renforcer la robustesse de la d{\'e}monstration de s{\^u}ret{\'e} pour l'ensemble des fonctions de s{\^u}ret{\'e}. ASTRID aura un c{\oe}ur innovant {\`a} coefficient de vidange sodium n{\'e}gatif, b{\'e}n{\'e}ficiera de la grande inertie thermique des RNR-Na pour l'{\'e}vacuation de la puissance r{\'e}siduelle, et soit {\'e}liminera par conception la r{\'e}action sodium{\textendash}eau, soit garantira l'absence de cons{\'e}quences sur la s{\^u}ret{\'e} le cas {\'e}ch{\'e}ant.},
	number = {4},
	urldate = {2018-10-29},
	journal = {Comptes Rendus Physique},
	author = {Gauch{\'e}, Fran{\c c}ois},
	month = may,
	year = {2012},
	keywords = {ASTRID, Fukushima, Prototype, RNR-Na, Safety, SFR, Sodium, S{\^u}ret{\'e}},
	pages = {365--371},
	file = {ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/394REYXX/Gauch{\'e} - 2012 - Generation IV reactors and the ASTRID prototype L.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/khuff/Zotero/storage/K3Y37YYQ/Gauch{\'e} - 2012 - Generation IV reactors and the ASTRID prototype L.pdf:application/pdf;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/VH4SXSCD/S1631070512000369.html:text/html;ScienceDirect Snapshot:/Users/khuff/Zotero/storage/CARHLTSA/S1631070512000369.html:text/html}
}

@misc{bae_arfc/transition-scenarios:_2018,
	title = {arfc/transition-scenarios: {Synergistic} {Spent} {Fuel} {Dynamics} {Within} the {European} {Union} {Edits}},
	shorttitle = {arfc/transition-scenarios},
	url = {https://zenodo.org/record/1656964},
	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 = {2018-11-28},
	publisher = {Zenodo},
	author = {Bae, Jin Whan and Chee, Gwendolyn and Huff, Kathryn and Kennelly, Tyler and PEP8 Speaks and Wilson, Paul and Park, Gyutae},
	month = nov,
	year = {2018},
	doi = {10.5281/zenodo.1656964},
	file = {Zenodo Snapshot:/home/teddy/Zotero/storage/QANFK89F/1656964.html:text/html}
}

@techreport{piet_fuel_2006,
	title = {Fuel {Cycle} {Scenario} {Definition}, {Evaluation}, and {Trade}-offs},
	url = {https://www.osti.gov/biblio/911563},
	abstract = {This report aims to clarify many of the issues being discussed within the AFCI program, including Inert Matrix Fuel (IMF) versus Mixed Oxide (MOX) fuel, single-pass versus multi-pass recycling, thermal versus fast reactors, potential need for transmutation of technetium and iodine, and the value of separating cesium and strontium. It documents most of the work produced by INL, ANL, and SNL personnel under their Simulation, Evaluation, and Trade Study (SETS) work packages during FY2005 and the first half of FY2006. This report represents the first attempt to calculate a full range of metrics, covering all four AFCI program objectives - waste management, proliferation resistance, energy recovery, and systematic management/economics/safety - using a combination of "static" calculations and a system dynamic model, DYMOND. In many cases, we examine the same issue both dynamically and statically to determine the robustness of the observations. All analyses are for the U.S. reactor fleet. This is a technical report, not aimed at a policy-level audience. A wide range of options are studied to provide the technical basis for identifying the most attractive options and potential improvements. Option improvement could be vital to accomplish before the AFCI program publishes definitive cost estimates. Information from this report will be extracted and summarized in future policy-level reports. Many dynamic simulations of deploying those options are included. There are few "control knobs" for flying or piloting the fuel cycle system into the future, even though it is dark (uncertain) and controls are sluggish with slow time response: what types of reactors are built, what types of fuels are used, and the capacity of separation and fabrication plants. Piloting responsibilities are distributed among utilities, government, and regulators, compounding the challenge of making the entire system work and respond to changing circumstances. We identify four approaches that would increase our ability to pilot the fuel cycle system: (1) have a recycle strategy that could be implemented before the 2030-2050 approximate period when current reactors retire so that replacement reactors fit into the strategy, (2) establish an option such as multi-pass blended-core IMF as a downward plutonium control knob and accumulate waste management benefits early, (3) establish fast reactors with flexible conversion ratio as a future control knob that slowly becomes available if/when fast reactors are added to the fleet, and (4) expand exploration of blended assemblies and cores, which appear to have advantages and agility. Initial results suggest multi-pass full-core MOX appears to be a less effective way than multi-pass blended core IMF to manage the fuel cycle system because it requires higher TRU throughput while more slowly accruing waste management benefits. Single-pass recycle approaches for LWRs (we did not study the VHTR) do not meet AFCI program objectives and could be considered a "dead end". Fast reactors appear to be effective options but a significant number of fast reactors must be deployed before the benefit of such strategies can be observed.},
	language = {English},
	number = {INL/EXT-06-11683},
	institution = {Idaho National Laboratory (INL)},
	author = {Piet, Steven J. and Matthern, Gretchen E. and Jacobson, Jacob J. and Laws, Christopher T. and Cadwallader, Lee C. and Yacout, Abdellatif M. and Hill, Robert N. and Smith, J. D. and Goldmann, Andrew S. and Bailey, George},
	year = {2006},
	doi = {10.2172/911563},
	file = {Full Text:/Users/khuff/Zotero/storage/BVA57XKP/Piet et al. - 2006 - Fuel Cycle Scenario Definition, Evaluation, and Tr.pdf:application/pdf;Full Text PDF:/Users/khuff/Zotero/storage/582DJE5D/Piet et al. - 2006 - Fuel Cycle Scenario Definition, Evaluation, and Tr.pdf:application/pdf;Snapshot:/Users/khuff/Zotero/storage/NFVREZWT/911563.html:text/html;Snapshot:/Users/khuff/Zotero/storage/2XJ4CPW7/911563.html:text/html}
}

@techreport{wims8_wims_1999,
	title = {{WIMS} - {A} {Modular} {Scheme} for {Neutronics} {Calculations}},
	institution = {Serco Assurance},
	author = {{WIMS8}},
	month = jul,
	year = {1999}
}