BEGIN:VCALENDAR VERSION:2.0 PRODID:-//CERN//INDICO//EN BEGIN:VEVENT SUMMARY:Pyrolysis and Plasma applied to Nuclear ion Exchange Resins Treatm ent DTSTART;VALUE=DATE-TIME:20171101T223000Z DTEND;VALUE=DATE-TIME:20171101T224500Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1212@events01.synchrotron.org.au DESCRIPTION:Speakers: hugo luis bianchi (Gerencia Química\, Comisión Nac ional de Energía Atómica\, CAC\, Av. Gral. Paz 1499 (1650) Buenos Aires\ , Argentina / ECyT\, UNSAM\, Martín de Irigoyen 3100 (1650) San Martín\, Argentina)\nSpent ion exchange resins (IER) represent an important waste stream that is generated during the operation of both light and heavy-wate r reactors. Over the past 60 years of nuclear activity Argentina has accum ulated over 300 m3 of spent IERs that to this day remain interim storage. With a view toward achieving a significant volume reduction and improved p roduct stability we are investigating a two-step process involving initial low-temperature (\n\nhttps://events01.synchrotron.org.au/event/51/contrib utions/1212/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1212/ END:VEVENT BEGIN:VEVENT SUMMARY:Emulsions as a powerful tool to design silica monoliths able to se lectively uptake radioactive caesium DTSTART;VALUE=DATE-TIME:20171101T220000Z DTEND;VALUE=DATE-TIME:20171101T221500Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1196@events01.synchrotron.org.au DESCRIPTION:Speakers: Jeremy Causse (Institut de Chimie Séparative de Mar coule (ICSM) - UMR5257 - CEA Marcoule)\nThis work deals with the developme nt of new templating routes to design porous nanostructured materials with innovative properties and/or easier to prepare. For example\, we have sho wn that copper hexacyanoferrate nanoparticles could stabilize High-Interna l Phase Emulsions or HIPE (**Mayer et al.\, J. Coll. Int. Sci.\, 2017\, do i.org/10.1016/j.jcis.2017.05.113**) that can be used in a second step as a template for functionalized monoliths. It is of great interest considerin g that these coordination polymers come from Prussian blue analogues famil y\, the most effective sorbent for caesium\, and therefore relevant in nuc lear decontamination purposes of 137Cs or 134Cs. To be active at oil/water interface and stabilize emulsions\, CuHCF particles have to be modified w ith a polyelectrolyte\, PDDA. The presence of CuHCF all around the oil dro plets of the emulsions makes these particles located all around the macrop ores inside the final silica monolith due to the fact that the oil droplet s are used as a template and should be therefore emptied after sol/gel gel ification of the emulsions in order to create macropores. However\, CuHCF can also be used without any PDDA surface modification. In this case\, CuH CF nanoparticles are hydrophilic and remain in the water phase of the HIPE . The water outer part of the HIPE is the place where sol/gel reactions oc cur. Therefore\, CuHCF nanoparticles are finally located in the monoliths walls if no PDDA is used. However CuHCF nanoparticles are still accessible to caesium in this case due to the mesoporosity of the walls because of t he use of surfactant in this case to stabilize the HIPE (**Causse et al.\, J. Mater. Chem. A\, 2014\, 2\, 9461**). And finally\, we have also develo ped a third synthesis route of functionalized silica monoliths with CuHCF\ , CoHCF and ZnHCF. In this latter exemple\, the HIPE is prepared only with the metal species\, either Cu or Co or Zn. After the sol/gel reaction a m eso/macroporous silica monoliths containing metal species is obtained. And finally after an impregnation step with K4[Fe(CN)6]\, the corresponding m etal hexacyanoferrate particles precipitate inside the porosity of the sil ica monolith (**Sommer-Marquez et al.\, RSC Adv.\, 2016\, 6\, 73475**).\nT his global study showed that we can play with particles of interest in ord er to change their location in the templating soft matter (HIPE) and there fore inside the final monolith. Results of inorganic materials characteriz ation (N2 adsoprtion/desorption\, SAXS\, SEM\, FTIR) as well as Cs sorptio n isotherms will be shown.\n\nhttps://events01.synchrotron.org.au/event/51 /contributions/1196/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1196/ END:VEVENT BEGIN:VEVENT SUMMARY:Inert matrix fuel deployment for reducing the plutonium stockpile in reactors DTSTART;VALUE=DATE-TIME:20171101T230000Z DTEND;VALUE=DATE-TIME:20171101T233000Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1190@events01.synchrotron.org.au DESCRIPTION:Speakers: Claude Degueldre (Engineering Department\, Lancaster University\, LA1 4YW\, UK)\nAbstract – The 450 reactors operating (Nov. 2016) around the world (30 countries) produce about 100 tonnes of plutoni um annually\, in spent fuel. Some amounts are separated through reprocessi ng. While the recycling of plutonium as MOX fuel derives additional energy from this resource\, it does little to address the issue of growing pluto nium inventories. If a political objective is to reduce the amount of plut onium\, then inert matrix fuel (IMF) provides an option for plutonium dest ruction. More generally\, the utilization of plutonium in IMF provides fle xibility in balancing the quantity of plutonium\, by enabling the net burn ing of plutonium. This approach is viable in existing cores (Gen II&III) t hat already utilize MOX fuel. IMF can be used both to manage plutonium inv entories and to contribute to reduce the long-term radiotoxicity of the sp ent fuel by minor actinide destruction. Some of these IMF materials are al so being considered for Gen IV reactors\, because of their advanced perfor mance\, economics\, safety features\, sustainability\, and application to waste minimization in a closed fuel cycle.\nSeveral promising candidate ma terials have been identified for both fast and thermal reactors: MgO (mag nesia)\, ZrO2 (zirconia)\, SiC (silicon carbide)\, Zr (alloys)\, ZrN (zirc onium nitride)\; some of these have undergone test irradiations and post i rradiation examination. These materials may be used as cylindrical pellets \, prismatic designed blocs\, or as micro-spheres utilized as sphere-pac o r kernels. They can be utilized at the fuel assembly level as prismatic (v ertical or horizontal) set up such as in Light Water Reactors\, Pressured Heavy Water Reactors or Liquid Metal Fast Reactor\, or\, as spherical such as in a High Temperature Gas-cooled Reactor. The fuel itself may be homo geneously composed of IMF or heterogeneously loaded with the IMF and urani um material. The assemblies may be homogeneously or heterogeneously loaded with the IMF\, and the reactor core may be homogeneously or heterogeneous ly loaded with IMF assemblies. These three levels\, i.e. fuel\, assembly a nd core\, of IMF utilization in LWR are considered within a homogeneous-he terogeneous concept scheme as recently reported in the IMF workshop. Model ling and testing IMF fuel performance and safety analysis have progressed. Fabrication methods have also been developed or adapted from existing te chnologies. System studies have identified strategies for both implementat ion of IMF fuel in existing reactors in the shorter term\, as well as in n ew reactors in the longer term. Finally for the backend the burned IMF sho uld be an attractive waste form to dispose or in specific conditions easy to reprocess.\nThe work to date has established the feasibility of these I MF materials\, and core loadings and reactor strategies for utilizing thes e fuels. Further developments are required before commercial deployment of IMF\, which will require additional resources. Additional in-pile irradia tions have been suggested\, both for normal operating and accident conditi ons. Further safety analysis and tests are required. Some development is n eeded for analysis tools and computer programs. Irradiations in commercial reactors should be undertaken in a staged approach as soon as possible: s egmented rods\, full-length rods\, then lead assemblies. IMF can play an important role in the future of nuclear power.\n\nhttps://events01.synchro tron.org.au/event/51/contributions/1190/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1190/ END:VEVENT BEGIN:VEVENT SUMMARY:Functionalised Titania and Zirconia Materials for Selective Actini de and Lanthanide Separations DTSTART;VALUE=DATE-TIME:20171101T224500Z DTEND;VALUE=DATE-TIME:20171101T230000Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1180@events01.synchrotron.org.au DESCRIPTION:Speakers: Jessica Veliscek Carolan (ANSTO)\nActinides and lant hanides are targets for partitioning from solutions of spent nuclear fuel. Traditionally\, actinide separation processes are based on liquid-liquid extraction. However\, use of solid phase sorbent materials has several adv antages such as the lack of organic solvent wastes. Framework materials ba sed on titania and zirconia have been developed and functionalised with or ganic ligands in order to impart selectivity. Titania and zirconia based f ramework materials were chosen due to their radiolytic and hydrolytic stab ility\, as well as the fact they can be easily converted to transmutation matrices or wasteforms once they are loaded with actinides. The framework materials used vary in complexity from simple nanoparticles to millimetre sized\, spherical\, hierarchically porous beads. In terms of organic ligan ds\, functionalisation with phosphonates\, amines and bistriazinylpyridine (BTP) has been performed to impart selectivity for lanthanides\, uranium or minor actinides.\n\nhttps://events01.synchrotron.org.au/event/51/contri butions/1180/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1180/ END:VEVENT BEGIN:VEVENT SUMMARY:Advanced Materials and Processes for Application to the Back-end o f the Nuclear Fuel Cycle DTSTART;VALUE=DATE-TIME:20171101T213000Z DTEND;VALUE=DATE-TIME:20171101T220000Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1174@events01.synchrotron.org.au DESCRIPTION:Speakers: Vittorio Luca (Comisión Nacional de Energía Atómi ca)\nThe nuclear industry generates a wide variety of radioactive waste st reams during reactor operations and maintenance and in virtually all parts of the fuel cycle. In order to improve the sustainability of the industry it is necessary to develop improved methods and processes for treating\, conditioning and disposing of this waste. The talk will provide an overvie w of research being conducted at the Comisión Nacional de Energía Atómi ca emphasizing the development of novel solid-extractants with the ability to selectively extract radionuclides from complex solutions and with comp ositions that facilitate end-of-life management by being able to be conver ted to extremely stable ceramics. Topics to be covered will include 1) a p roposed process for the conversion of spent polymeric ion exchange resins to stable pyropolymer and carbon materials and their subsequent immobiliza tion\, 2) synthesis of coordination polymers suitable for the selective ex traction of radiolanthanides and their subsequent immobilization\, 3) pote ntial new targets for a cleaner production of Mo-99 and 4) the use of phen olic resins as matrices for spent organic and inorganic ion exchange media .\n\nhttps://events01.synchrotron.org.au/event/51/contributions/1174/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1174/ END:VEVENT BEGIN:VEVENT SUMMARY:Highly porous and stable metal–organic frameworks for uranium ex traction DTSTART;VALUE=DATE-TIME:20171101T221500Z DTEND;VALUE=DATE-TIME:20171101T223000Z DTSTAMP;VALUE=DATE-TIME:20260416T051046Z UID:indico-contribution-342-1163@events01.synchrotron.org.au DESCRIPTION:Speakers: Michael Carboni (CEA)\nTransformative technologies a re needed in order to achieve economic uranium extraction from waste to ge nerate a new fuel or for a safe storage. Metal–organic frameworks (MOFs) are a class of hybrid materials composed of organic bridging ligands coor dinated to metal ions or metal ion clusters. The result is the formation o f a porous crystalline solid that possess adequate stability in aqueous so lution for potential application in U extraction. These materials can sele ctively precipitate with a specific metal to extract it or they have large pore apertures to facilitate the transport of hydrated actinide\nions thr ough the interior of the frameworks for the extraction. In this way pollut ants such as actinides can be targeted for selective precipitation as a MO F or bind inside the framework by the ligand. This material can be easily recovered by simple filtration or centrifugation and actinide can be store d after a thermal treatment of the material to finally generate an origina l strategy to combine extraction and storage.\n\nhttps://events01.synchrot ron.org.au/event/51/contributions/1163/ LOCATION: URL:https://events01.synchrotron.org.au/event/51/contributions/1163/ END:VEVENT END:VCALENDAR