diff --git a/bibliography.bib b/bibliography.bib
index 1446849..cbe3ced 100644
--- a/bibliography.bib
+++ b/bibliography.bib
@@ -1,44 +1,48 @@
 
-@article{huff_fundamental_2016,
-	title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework},
-	volume = {94},
-	issn = {0965-9978},
-	url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229},
-	doi = {10.1016/j.advengsoft.2016.01.014},
-	abstract = {As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.},
-	urldate = {2016-02-12},
-	journal = {Advances in Engineering Software},
-	author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.},
-	month = apr,
-	year = {2016},
-	keywords = {agent based modeling, agent based modeling, and Science, Computer Science - Computational Engineering, Computer Science - Computational Engineering, Finance, and Science, Computer Science - Mathematical Software, Computer Science - Mathematical Software, Computer Science - Multiagent Systems, Computer Science - Multiagent Systems, Computer Science - Software Engineering, Computer Science - Software Engineering, D.2.4, D.2.4, D.2.13, D.2.13, Finance, I.6.7, I.6.7, I.6.8, I.6.8, Nuclear Engineering, Nuclear Engineering, Nuclear fuel cycle, Nuclear Fuel Cycle, Object orientation, Object orientation, Simulation, Simulation, Systems analysis, Systems Analysis},
-	pages = {46--59},
-	annote = {arXiv: 1509.03604},
-	file = {arXiv\:1509.03604 PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/4FI3T63Q/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/F9KVM9DZ/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv.org Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/HXSDS7VW/1509.html:text/html;arXiv.org Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/WQVTXAN2/1509.html:text/html;fundamentals.pdf:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/BRJECDWC/fundamentals.pdf:application/pdf;fundamentals.pdf:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/C6G4NQJH/fundamentals.pdf:application/pdf;ScienceDirect Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/E7DK64AA/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/63CHUQ54/login.html:text/html;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/EVBNKXMA/S0965997816300229.html:text/html;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/JCCZAZB3/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{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 ‘but for’ baseline and the
+much discussed ‘nuclear renaissance.’ 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:/home/dkadkf/Zotero/storage/29IIH4F6/Joskow and Parsons - 2012 - The Future of Nuclear Power After Fukushima.pdf:application/pdf;Snapshot:/home/dkadkf/Zotero/storage/DW6XA46Q/70857.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 “must test” 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’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},
+@phdthesis{fabbris_optimisation_2014,
+	type = {phdthesis},
+	title = {Optimisation multi-physique et multi-critère des coeurs de {RNR}-{Na} : application au concept {CFV}},
+	shorttitle = {Optimisation multi-physique et multi-critère des coeurs de {RNR}-{Na}},
+	url = {https://tel.archives-ouvertes.fr/tel-01133491/document},
+	abstract = {La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo-hydraulique, thermomécanique du combustible, physique du cycle, etc.). Le problème est aussi de type multi-objectif (plusieurs performances) à grand nombre de dimensions (plusieurs dizaines de paramètres de conception).Les codes de calculs déterministes utilisés traditionnellement pour la caractérisation des coeurs demandant d’importantes ressources informatiques, l’approche de conception classique rend difficile l’exploration et l’optimisation de nouveaux concepts innovants. Afin de pallier ces difficultés, une nouvelle méthodologie a été développée lors de ces travaux de thèse. Ces travaux sont basés sur la mise en oeuvre et la validation de schémas de calculs neutronique et thermo-hydraulique pour disposer d’un outil de caractérisation d’un coeur de réacteur à neutrons rapides à caloporteur sodium tant du point de vue des performances neutroniques que de son comportement en transitoires accidentels.La méthodologie mise en oeuvre s’appuie sur la construction de modèles de substitution (ou métamodèles) aptes à remplacer la chaîne de calcul neutronique et thermo-hydraulique. Des méthodes mathématiques avancées pour la planification d’expériences, la construction et la validation des métamodèles permettent de remplacer cette chaîne de calcul par des modèles de régression au pouvoir de prédiction élevé.La méthode est appliquée à un concept innovant de coeur à Faible coefficient de Vidange sur un très large domaine d’étude, et à son comportement lors de transitoires thermo-hydrauliques non protégés pouvant amener à des situations incidentelles, voire accidentelles. Des analyses globales de sensibilité permettent d’identifier les paramètres de conception influents sur la conception du coeur et son comportement en transitoire. Des optimisations multicritères conduisent à des nouvelles configurations dont les performances sont parfois significativement améliorées. La validation des résultats produits au cours de ces travaux de thèse démontre la pertinence de la méthode au stade de la préconception d’un coeur de réacteur à neutrons rapides refroidi au sodium.},
+	language = {fr},
+	urldate = {2017-07-21},
+	school = {Université de Grenoble},
+	author = {Fabbris, Olivier},
 	month = oct,
-	year = {2016},
-	keywords = {Fuel cycle simulator, Transition analysis, Unit tests},
-	pages = {88--95},
-	file = {ScienceDirect Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/9H5GZ7QA/Brown et al. - 2016 - Identification of fuel cycle simulator functionali.pdf:application/pdf;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/NFQC7CXG/S0306454916303383.html:text/html;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/Z6WQH4Q4/S0306454916303383.html:text/html}
+	year = {2014},
+	annote = {85 - geometry
+91 - initial fuel
+ },
+	file = {Full Text PDF:/home/dkadkf/Zotero/storage/AI9FANBF/Fabbris - 2014 - Optimisation multi-physique et multi-critère des c.pdf:application/pdf;Snapshot:/home/dkadkf/Zotero/storage/54B5PP4P/tel-01133491.html:text/html}
 }
 
 @techreport{boucher_benchmark_2012,
@@ -48,181 +52,29 @@ @techreport{boucher_benchmark_2012
 	author = {Boucher, L.},
 	month = jun,
 	year = {2012},
-	file = {nsc-wpfc-doc2012-16.pdf:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/3SSZVRG4/nsc-wpfc-doc2012-16.pdf:application/pdf}
-}
-
-@inproceedings{carre_overview_2009,
-	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},
-	urldate = {2016-10-27},
-	booktitle = {proceedings of global},
-	author = {Carré, Frank and Delbecq, Jean-Marie},
-	year = {2009},
-	file = {[PDF] researchgate.net:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/93TK25DV/Carré and Delbecq - 2009 - Overview on the French nuclear fuel cycle strategy.pdf:application/pdf}
-}
-
-@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:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/AVP329PE/epjn150066.html:text/html;Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/HIBGZJTC/epjn150066.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™ (European Pressurized water Reactors) is studied. EPR™ 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™ 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™ 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™ 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 = {EPR™, FAST REACTORS, Fuel reprocessing, Nuclear energy, plutonium, SFR, Symbiotic nuclear systems, Thermal reactors},
-	pages = {356--362},
-	file = {ScienceDirect Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/4D8VC2KI/Martin and Coquelet-Pascal - 2017 - Symbiotic equilibrium between Sodium Fast Reactors.pdf:application/pdf;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/VPCQBPZW/S0306454916308076.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},
-	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:/home/teddy/.mozilla/firefox/yq0yx47z.default/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}
-}
-
-@misc{noauthor_nuclear_2017,
-	title = {Nuclear {Energy} in {Sweden} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-o-s/sweden.aspx},
-	urldate = {2017-04-17},
-	month = jan,
-	year = {2017},
-	file = {Nuclear Energy in Sweden - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/H69GDAIC/sweden.html:text/html}
-}
-
-@misc{noauthor_nuclear_2017-1,
-	title = {Nuclear {Energy} in {Finland} {\textbar} {Finnish} {Nuclear} {Power} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-a-f/finland.aspx},
-	urldate = {2017-04-17},
-	month = jan,
-	year = {2017},
-	file = {Nuclear Energy in Finland | Finnish Nuclear Power - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/XCN8ZJID/finland.html:text/html}
-}
-
-@misc{noauthor_nuclear_2017-2,
-	title = {Nuclear {Power} in {Belgium} {\textbar} {Belgian} {Nuclear} {Energy} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-a-f/belgium.aspx},
-	urldate = {2017-04-17},
-	month = feb,
-	year = {2017},
-	file = {Nuclear Power in Belgium | Belgian Nuclear Energy - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/CGEFNSCQ/belgium.html:text/html}
-}
-
-@book{__2009,
-	title = {{КОНСТРУКЦИИ} ТВЭЛОВ, КАНАЛОВ И АКТИВНЫХ ЗОН ЭНЕРГЕТИЧЕСКИХ РЕАКТОРОВ},
-	abstract = {При выполнении курсового проектирования повышенной сложно⬚
-сти, дипломной или выпускной работы, связанных с нейтронно⬚физиче⬚
-ским и теплофизическим расчетом реакторной установки, в первую оче⬚
-редь возникают вопросы принятия тех или иных решений, по конструк⬚
-ции твэл, тепловыделяющих сборок, кассет или каналов, компоновок
-оборудования и конструктивного решения установки в целом. От пра⬚
-вильности принятых решений зависит в конечном счете успех расчета.
-Вместе с тем существует целый ряд отработанных конструктивных
-решений для ядерных установок различного типа, которые содержатся
-многочисленной разрозненной литературе.
-Прибегая к данным такой литературы, проектант невольно огра⬚
-ничивает свои знания только теми, которые справедливы для одного
-конкретного типа реактора, в то время как конструктивные решения
-для других типов реакторов для него неиспользованными. Такой под⬚
-ход особенно нежелателен для учебного процесса так как существует
-большое разнообразие как реакторов, так и их конструкций.
-В настоящем учебном пособии представлены существующие кон⬚
-структивные решения для энергетических реакторов на тепловых ней⬚
-тронах различного типа и их конструктивные элементы:
-• водоохлаждаемые реакторы – ВВЭР, ВК и с графитовым замедли⬚
-телем;
-• газоохлаждаемые Magnox, AGR, HTGR;
-• натрийохлаждаемые с графитовым замедлителем.
-Учебное пособие может быть полезно магистрантам, студентам об⬚
-учающимся по направлению 010700 «Физика» при выполнении курсово⬚
-го проектирования, дипломных и выпускных квалификационных работ.},
-	author = {Колпаков, Г.Н. and Селиваникова, О.В.},
-	year = {2009}
-}
-
-@misc{noauthor_nuclear_2017-3,
-	title = {Nuclear {Power} in the {Czech} {Republic} {\textbar} {Nuclear} {Power} in {Czechia} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-a-f/czech-republic.aspx},
-	urldate = {2017-04-17},
-	month = feb,
-	year = {2017},
-	file = {Nuclear Power in the Czech Republic | Nuclear Power in Czechia - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/9XR3KD8D/czech-republic.html:text/html}
-}
-
-@misc{noauthor_nuclear_2017-4,
-	title = {Nuclear {Power} in {Poland} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-o-s/poland.aspx},
-	urldate = {2017-04-18},
-	month = apr,
-	year = {2017},
-	file = {Nuclear Power in Poland - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/827SNI7S/poland.html:text/html}
-}
-
-@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}
+	file = {nsc-wpfc-doc2012-16.pdf:/home/dkadkf/Zotero/storage/3SSZVRG4/nsc-wpfc-doc2012-16.pdf:application/pdf}
 }
 
-@misc{noauthor_nuclear_2017-5,
-	title = {Nuclear {Power} in {Germany} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-g-n/germany.aspx},
-	urldate = {2017-04-17},
-	month = apr,
-	year = {2017},
-	file = {Nuclear Power in Germany - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/B6AW5MJJ/germany.html:text/html}
+@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:/home/dkadkf/Zotero/storage/II69N986/Hugelmann and Greneche - 1999 - MELOX fuel fabrication plant operational feedback.pdf:application/pdf}
 }
 
-@misc{iaea_pris_nodate,
-	title = {{PRIS} - {Home}},
-	url = {https://www.iaea.org/pris/},
-	urldate = {2017-04-03},
-	author = {IAEA},
-	file = {PRIS - Home:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/KJU7EXF4/pris.html:text/html}
+@book{schneider_spent_2008,
+	title = {Spent nuclear fuel reprocessing in {France}},
+	url = {http://www.psr.org/nuclear-bailout/resources/spent-nuclear-fuel.pdf},
+	author = {Schneider, Mycle and Marignac, Yves},
+	year = {2008},
+	annote = {La Hague - 1100 tons/year
+ }
 }
 
 @techreport{iaea_management_2007,
@@ -259,13 +111,14 @@ @techreport{iaea_management_2007
 	pages = {108}
 }
 
-@misc{noauthor_nuclear_2016,
-	title = {Nuclear {Power} in {Bulgaria} {\textbar} {Bulgarian} nuclear energy - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-a-f/bulgaria.aspx},
-	urldate = {2017-04-18},
-	month = oct,
-	year = {2016},
-	file = {Nuclear Power in Bulgaria | Bulgarian nuclear energy - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/8TISDGZX/bulgaria.html:text/html}
+@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:/home/dkadkf/Zotero/storage/KJU7EXF4/pris.html:text/html}
 }
 
 @misc{world_nuclear_association_nuclear_2017,
@@ -275,124 +128,146 @@ @misc{world_nuclear_association_nuclear_2017
 	author = {World Nuclear Association},
 	month = feb,
 	year = {2017},
-	file = {Nuclear Power in the European Union - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/VG9QDBRU/european-union.html:text/html}
+	file = {Nuclear Power in the European Union - World Nuclear Association:/home/dkadkf/Zotero/storage/VG9QDBRU/european-union.html:text/html}
 }
 
-@misc{noauthor_nuclear_2017-6,
-	title = {Nuclear {Power} in the {United} {Kingdom} {\textbar}{UK} {Nuclear} {Energy} - {World} {Nuclear} {Association}},
-	url = {http://www.world-nuclear.org/information-library/country-profiles/countries-t-z/united-kingdom.aspx},
-	urldate = {2017-04-17},
-	month = apr,
-	year = {2017},
-	file = {Nuclear Power in the United Kingdom |UK Nuclear Energy - World Nuclear Association:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/ZCJ4UEPF/united-kingdom.html:text/html}
+@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}
 }
 
-@book{schneider_spent_2008,
-	title = {Spent nuclear fuel reprocessing in {France}},
-	url = {http://www.psr.org/nuclear-bailout/resources/spent-nuclear-fuel.pdf},
-	author = {Schneider, Mycle and Marignac, Yves},
-	year = {2008},
-	annote = {La Hague - 1100 tons/year
- }
+@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}
 }
 
-@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:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/II69N986/Hugelmann and Greneche - 1999 - MELOX fuel fabrication plant operational feedback.pdf:application/pdf}
+@article{wigeland_nuclear_2014,
+	title = {Nuclear {Fuel} {Cycle} {Evaluation} and {Screening}–{Final} {Report}},
+	url = {https://fuelcycleevaluation.inl.gov/Shared%20Documents/ES%20Main%20Report.pdf},
+	urldate = {2017-03-29},
+	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:/home/dkadkf/Zotero/storage/WEVPB9EQ/ES Main Report.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:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/SZH27EZ6/search.html:text/html}
+@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:/home/dkadkf/Zotero/storage/WSSD6JHQ/Piet et al. - 2010 - Implications of Fast Reactor Transuranic Conversio.pdf:application/pdf}
 }
 
-@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 ‘but for’ baseline and the
-much discussed ‘nuclear renaissance.’ 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:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/29IIH4F6/Joskow and Parsons - 2012 - The Future of Nuclear Power After Fukushima.pdf:application/pdf;Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/DW6XA46Q/70857.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}
 }
 
-@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,
+@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},
+	annote = {Regional (European) scenario of partitioning and transmutation to lessen SNF load},
+	file = {Snapshot:/home/dkadkf/Zotero/storage/2STTNZDS/264479296_Study_on_partitioning_and_transmutation_as_a_possible_option_for_spent_fuel_management.pdf:application/pdf}
+}
+
+@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},
-	note = {Google-Books-ID: TrwfBgAAQBAJ},
-	keywords = {History / Europe / Western, Political Science / Public Policy / Science \& Technology Policy, Technology \& Engineering / Power Resources / Nuclear}
+	keywords = {Nuclear fuel cycle, Nuclear reactor safety, Sodium fast reactors, Transmutation},
+	pages = {130--139},
+	file = {ScienceDirect Full Text PDF:/home/dkadkf/Zotero/storage/2APV2MPJ/Gabrielli et al. - 2015 - ASTRID-like Fast Reactor Cores for Burning Plutoni.pdf:application/pdf;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/I78CKW34/S1876610214026927.html:text/html}
 }
 
-@article{marsaultmarie-sophie_pre-conceptual_2012,
-	title = {Pre-conceptual design study of {ASTRID} core},
-	url = {https://www.researchgate.net/profile/Frederic_Varaine/publication/282657288_Pre-conceptual_design_study_of_ASTRID_core/links/56166d1908ae37cfe4090bb7.pdf},
-	urldate = {2017-05-19},
-	author = {MARSAULT–Marie-Sophie, Frédéric VARAINE-Philippe and CONTI, CHENAUD-Bruno BERNARDIN–Alain and FONTAINE, Pierre SCIORA-Christophe VENARD–Bruno and MARTIN, Nicolas DEVICTOR-Laurent and VERRIER, Anne-Claire SCHOLER–Denis},
+@techreport{noauthor_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’Aube – CSA)},
+	language = {English},
+	urldate = {2017-06-24},
+	institution = {Commission Nationae D'Evaluation},
 	month = jun,
-	year = {2012},
-	file = {[PDF] researchgate.net:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/2B4SNXP4/MARSAULT–Marie-Sophie et al. - Pre-conceptual design study of ASTRID core.pdf:application/pdf}
+	year = {2015},
+	pages = {120},
+	file = {CNE2 - Reports of the CNE2 - 2007 to this day:/home/dkadkf/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 “regional” 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 = {ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/3PMMTCTG/S0029549304003759.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},
+	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 = {epjn150066.pdf:/home/dkadkf/Zotero/storage/HA6HH8VJ/epjn150066.pdf:application/pdf;[HTML] epj-n.org:/home/dkadkf/Zotero/storage/ZHNXV2WH/epjn150066.html:text/html;Snapshot:/home/dkadkf/Zotero/storage/8URTHTBQ/epjn150066.html:text/html}
 }
 
-@inproceedings{carre_overview_2009-1,
-	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},
-	booktitle = {proceedings of global},
-	author = {Carré, Frank and Delbecq, Jean-Marie},
-	year = {2009},
-	file = {[PDF] researchgate.net:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/A2XM22QS/Carré and Delbecq - 2009 - Overview on the French nuclear fuel cycle strategy.pdf:application/pdf}
+@article{coquelet-pascal_comparison_nodate,
+	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},
+	urldate = {2017-06-17},
+	author = {Coquelet-Pascal, Christine and Meyer, Maryan and Girieud, Richard},
+	file = {Snapshot:/home/dkadkf/Zotero/storage/USKER87I/search.html:text/html}
 }
 
 @article{madic_futuristic_2007,
@@ -409,77 +284,63 @@ @article{madic_futuristic_2007
 	year = {2007},
 	keywords = {Actinide alloys and compounds},
 	pages = {23--27},
-	file = {ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/QNKQI4NX/S0925838807012029.html:text/html}
+	file = {ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/QNKQI4NX/S0925838807012029.html:text/html}
 }
 
-@article{coquelet-pascal_comparison_nodate,
-	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},
-	urldate = {2017-06-17},
-	author = {Coquelet-Pascal, Christine and Meyer, Maryan and Girieud, Richard},
-	file = {Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/USKER87I/search.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},
+	booktitle = {Proceedings of {GLOBAL}},
+	author = {Carre, Frank and Delbecq, Jean-Michel},
+	year = {2009},
+	file = {[PDF] researchgate.net:/home/dkadkf/Zotero/storage/A2XM22QS/Carré and Delbecq - 2009 - Overview on the French nuclear fuel cycle strategy.pdf:application/pdf}
 }
 
-@article{freynet_multiobjective_2016-1,
-	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},
-	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 = {epjn150066.pdf:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/HA6HH8VJ/epjn150066.pdf:application/pdf;[HTML] epj-n.org:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/ZHNXV2WH/epjn150066.html:text/html;Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/8URTHTBQ/epjn150066.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 “regional” 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 = {ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/3PMMTCTG/S0029549304003759.html:text/html}
 }
 
-@phdthesis{fabbris_optimisation_2014,
-	type = {phdthesis},
-	title = {Optimisation multi-physique et multi-critère des coeurs de {RNR}-{Na} : application au concept {CFV}},
-	shorttitle = {Optimisation multi-physique et multi-critère des coeurs de {RNR}-{Na}},
-	url = {https://tel.archives-ouvertes.fr/tel-01133491/document},
-	abstract = {La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo-hydraulique, thermomécanique du combustible, physique du cycle, etc.). Le problème est aussi de type multi-objectif (plusieurs performances) à grand nombre de dimensions (plusieurs dizaines de paramètres de conception).Les codes de calculs déterministes utilisés traditionnellement pour la caractérisation des coeurs demandant d’importantes ressources informatiques, l’approche de conception classique rend difficile l’exploration et l’optimisation de nouveaux concepts innovants. Afin de pallier ces difficultés, une nouvelle méthodologie a été développée lors de ces travaux de thèse. Ces travaux sont basés sur la mise en oeuvre et la validation de schémas de calculs neutronique et thermo-hydraulique pour disposer d’un outil de caractérisation d’un coeur de réacteur à neutrons rapides à caloporteur sodium tant du point de vue des performances neutroniques que de son comportement en transitoires accidentels.La méthodologie mise en oeuvre s’appuie sur la construction de modèles de substitution (ou métamodèles) aptes à remplacer la chaîne de calcul neutronique et thermo-hydraulique. Des méthodes mathématiques avancées pour la planification d’expériences, la construction et la validation des métamodèles permettent de remplacer cette chaîne de calcul par des modèles de régression au pouvoir de prédiction élevé.La méthode est appliquée à un concept innovant de coeur à Faible coefficient de Vidange sur un très large domaine d’étude, et à son comportement lors de transitoires thermo-hydrauliques non protégés pouvant amener à des situations incidentelles, voire accidentelles. Des analyses globales de sensibilité permettent d’identifier les paramètres de conception influents sur la conception du coeur et son comportement en transitoire. Des optimisations multicritères conduisent à des nouvelles configurations dont les performances sont parfois significativement améliorées. La validation des résultats produits au cours de ces travaux de thèse démontre la pertinence de la méthode au stade de la préconception d’un coeur de réacteur à neutrons rapides refroidi au sodium.},
-	language = {fr},
-	urldate = {2017-07-21},
-	school = {Université de Grenoble},
-	author = {Fabbris, Olivier},
-	month = oct,
-	year = {2014},
-	annote = {85 - geometry
-91 - initial fuel
- },
-	file = {Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/AI9FANBF/Fabbris - 2014 - Optimisation multi-physique et multi-critère des c.pdf:application/pdf;Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/54B5PP4P/tel-01133491.html:text/html}
-}
+@article{varaine_pre-conceptual_2012,
+	title = {Pre-conceptual design study of {ASTRID} core},
+	url = {https://www.researchgate.net/profile/Frederic_Varaine/publication/282657288_Pre-conceptual_design_study_of_ASTRID_core/links/56166d1908ae37cfe4090bb7.pdf},
+	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. 
 
-@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},
-	annote = {Regional (European) scenario of partitioning and transmutation to lessen SNF load},
-	file = {Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/2STTNZDS/264479296_Study_on_partitioning_and_transmutation_as_a_possible_option_for_spent_fuel_management.pdf:application/pdf}
+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].},
+	urldate = {2017-05-19},
+	author = {Varaine, Frederic and Chenaud, Marie-Sophie and Marsault, Philippe and Bernardin, Bruno and Conti, Alain and Sciora, Pierre and Venard, Christophe and Fontaine, Bruno and Martin, Laurent and Mignot, Gerard},
+	month = jun,
+	year = {2012},
+	file = {[PDF] researchgate.net:/home/dkadkf/Zotero/storage/2B4SNXP4/MARSAULT–Marie-Sophie et al. - Pre-conceptual design study of ASTRID core.pdf:application/pdf}
 }
 
-@misc{noauthor_cne2_nodate,
-	title = {{CNE}2 - {Reports} of the {CNE}2 - 2007 to this day},
-	url = {https://www.cne2.fr/index.php/en/cne-2-2007-to-this-day},
-	urldate = {2017-06-24},
-	file = {CNE2 - Reports of the CNE2 - 2007 to this day:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/9WF2G3QN/cne-2-2007-to-this-day.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}
 }
 
 @article{sutharshan_ap1000tm_2011,
@@ -498,38 +359,100 @@ @article{sutharshan_ap1000tm_2011
 	year = {2011},
 	keywords = {core operating parameters, Generation III+ reactor, modular design, passive safety, probabilistic risk assessment, PWR},
 	pages = {293--302},
-	file = {ScienceDirect Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/2D66N8K4/Sutharshan et al. - 2011 - The AP1000TM Reactor Passive Safety and Modular D.pdf:application/pdf;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/E87IC8RM/S1876610211015475.html:text/html}
+	file = {ScienceDirect Full Text PDF:/home/dkadkf/Zotero/storage/2D66N8K4/Sutharshan et al. - 2011 - The AP1000TM Reactor Passive Safety and Modular D.pdf:application/pdf;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/E87IC8RM/S1876610211015475.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}
+@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:/home/dkadkf/Zotero/storage/SZH27EZ6/search.html:text/html}
 }
 
-@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:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/WSSD6JHQ/Piet et al. - 2010 - Implications of Fast Reactor Transuranic Conversio.pdf:application/pdf}
+@article{huff_fundamental_2016,
+	title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework},
+	volume = {94},
+	issn = {0965-9978},
+	url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229},
+	doi = {10.1016/j.advengsoft.2016.01.014},
+	abstract = {As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.},
+	urldate = {2016-02-12},
+	journal = {Advances in Engineering Software},
+	author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.},
+	month = apr,
+	year = {2016},
+	keywords = {Nuclear fuel cycle, agent based modeling, 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 Engineering, Object orientation, Systems analysis, Nuclear Fuel Cycle, Simulation, Finance, and Science, Computer Science - Computational Engineering, Systems Analysis},
+	pages = {46--59},
+	annote = {arXiv: 1509.03604},
+	file = {arXiv\:1509.03604 PDF:/home/dkadkf/Zotero/storage/F9KVM9DZ/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/home/dkadkf/Zotero/storage/4FI3T63Q/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv.org Snapshot:/home/dkadkf/Zotero/storage/HXSDS7VW/1509.html:text/html;arXiv.org Snapshot:/home/dkadkf/Zotero/storage/WQVTXAN2/1509.html:text/html;fundamentals.pdf:/home/dkadkf/Zotero/storage/C6G4NQJH/fundamentals.pdf:application/pdf;fundamentals.pdf:/home/dkadkf/Zotero/storage/BRJECDWC/fundamentals.pdf:application/pdf;ScienceDirect Full Text PDF:/home/dkadkf/Zotero/storage/E7DK64AA/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/JCCZAZB3/S0965997816300229.html:text/html;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/63CHUQ54/login.html:text/html;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/EVBNKXMA/S0965997816300229.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},
+@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 “must test” 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’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:/home/dkadkf/Zotero/storage/9H5GZ7QA/Brown et al. - 2016 - Identification of fuel cycle simulator functionali.pdf:application/pdf;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/Z6WQH4Q4/S0306454916303383.html:text/html;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/NFQC7CXG/S0306454916303383.html:text/html}
+}
+
+@article{freynet_multiobjective_2016-1,
+	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:/home/dkadkf/Zotero/storage/AVP329PE/epjn150066.html:text/html;Snapshot:/home/dkadkf/Zotero/storage/HIBGZJTC/epjn150066.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™ (European Pressurized water Reactors) is studied. EPR™ 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™ 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™ 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™ 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 = {2015},
-	keywords = {Nuclear fuel cycle, Nuclear reactor safety, Sodium fast reactors, Transmutation},
-	pages = {130--139},
-	file = {ScienceDirect Full Text PDF:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/2APV2MPJ/Gabrielli et al. - 2015 - ASTRID-like Fast Reactor Cores for Burning Plutoni.pdf:application/pdf;ScienceDirect Snapshot:/home/teddy/.mozilla/firefox/yq0yx47z.default/zotero/storage/I78CKW34/S1876610214026927.html:text/html}
+	year = {2017},
+	keywords = {Nuclear energy, SFR, FAST REACTORS, plutonium, EPR™, Fuel reprocessing, Symbiotic nuclear systems, Thermal reactors},
+	pages = {356--362},
+	file = {ScienceDirect Full Text PDF:/home/dkadkf/Zotero/storage/4D8VC2KI/Martin and Coquelet-Pascal - 2017 - Symbiotic equilibrium between Sodium Fast Reactors.pdf:application/pdf;ScienceDirect Snapshot:/home/dkadkf/Zotero/storage/VPCQBPZW/S0306454916308076.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}
+}
+
+@misc{bae_arfc/transition-scenarios:_2017,
+	title = {arfc/transition-scenarios: {Synergistic} {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union}},
+	shorttitle = {arfc/transition-scenarios},
+	url = {https://zenodo.org/record/858671#.WahAzHWGPdJ},
+	abstract = {This release contains code to reproduce the plots used in the paper Synergistic Spent Nuclear Fuel Dynamics Within the European Union},
+	urldate = {2017-08-31},
+	publisher = {Advanced Reactors and Fuel Cycles Research Group},
+	author = {Bae, Jin Whan and Park, Gyu Tae and Huff, Kathryn},
+	month = aug,
+	year = {2017},
+	note = {DOI: 10.5281/zenodo.858671},
+	file = {Zenodo Snapshot:/home/dkadkf/Zotero/storage/B8JXTTQ8/858671.html:text/html}
 }
\ No newline at end of file