Agency: European Commission | Branch: FP7 | Program: CSA-CA | Phase: Fission-2011-3.5.1 | Award Amount: 1.55M | Year: 2012
Creating a sustainable network in biological dosimetry that involves a large number of experienced laboratories throughout the EU will significantly improve the accident and emergency response capabilities in case of a large-scale radiological emergency. A well organised cooperated action involving EU laboratories will offer the only chance for a fast and trustworthy dose assessment urgently needed in an emergency situation. The goal of RENEB is to establish a sustainable European network in biological dosimetry involving 23 organisations from 16 countries identified by the TENEB survey, that will guarantee highest efficiency in processing and scoring of biological samples for fast, reliable results implemented in the EU emergency management. This goal will be achieved through 5 tasks: 1) To create an operational basis of the network, based on coordination of the existing reliable and proven methods in biological dosimetry. 2) To expand and improve the network implementing appropriate new, molecular biology methods and integrating new partners. 3) To assure high quality standards by education and training activities of members and interested non-members. Here, special focus will be placed on quality assurance and management regarding the performed assays and involved laboratories. 4) To develop an operational structure of the network including contacts to national first responders, a well organised transnational infrastructure to facilitate cross-border transport of human biological samples, a long term funding strategy and to prepare an agenda to transform RENEB into a legal organisation. 5) To guarantee dissemination of knowledge by providing access to internal and external communication platforms and databases and close cooperation with national and global emergency preparedness systems and organisations. All of these activities are strictly complementary to on-going projects in the EU Security Research Programme, specifically to MULTIBIODOSE and to EURADOS.
Agency: European Commission | Branch: FP7 | Program: CSA-CA | Phase: Fission-2013-6.0.1 | Award Amount: 1.96M | Year: 2013
The ARCADIA project has been conceived so as to provide a twofold support to the further development of nuclear research programs in the NMS, targeting two major areas included in the Strategic Research and Innovation Agenda of SNETP: ESNII, through the support of the ALFRED project towards its realization in Romania, and NUGENIA, approaching remaining safety aspects of Gen III/III\ that could be built in Lithuania, Poland ,Czech Republic and Slovenia. On one hand, it focuses on the identification of the primary needs for the ALFRED project, mainly to what concerns E&T, supporting Infrastructures and Regulatory aspects (and integrating for the R&D needs the outcomes of other research projects in a common frame of National and Regional needs); on the other hand, it investigates the existing National and Regional supporting structures with a particular attention to the ones in Romania and in all the participating New Member States for defining a map of competences potentially eligible to satisfy the previously identified needs. The entire work dedicated to ALFRED project will be performed within the frame of strategic orientations to be compiled for the ALFRED project, and with the scientific, technical and regulatory advising of the costituendum provisional ALFRED consortium on one side, and of the Romanian Regulatory Body on the other side. Finally, Networking, Cooperation and Dissemination activities will provide the connection with the international scientific community, with the European institutional organizations and with the general public, for ensuring the soundness and palatability of both Gen III/III\ and ALFRED projects in general.
Agency: European Commission | Branch: FP7 | Program: CSA-CA | Phase: Fission-2013-6.0.2 | Award Amount: 1.09M | Year: 2013
Education, training and information to the general public are key factors in the governance of ionising radiation risks. Communication about ionising radiation with the general public has to to be further improved, as highlighted also by the 2011 accident in Japan. An effort is needed to analyse the state of the art and the existing needs in education, training and information, and to coordinate the information and communication about ionising radiation at European level. This proposal aims specifically at coordinating the information and communication strategies related to ionising radiation for the general public, in order to get a better understanding of the effects of ionising radiation, taking also into consideration the lessons learnt from the 2011 accident in Fukushima (Japan). It addresses the call Fission-2013-6.0.2: Education / training / information towards the public. The proposal, further referred to by the acronym EAGLE (Enhancing educAtion, traininG and communication processes for informed behaviors and decision-making reLatEd to ionizing radiation risks), will help to identify and disseminate good practices in information and communication processes related to ionising radiation. For this purpose, the consortium intends to review national and international data, tools and methods as well as institutional work in order to identify education, information and communication needs and coordination possibilities at European level. The lessons learned from the nuclear accident in Fukushima will also provide a valuable input. The main goal of the project is to enhance public understanding of ionizing radiation and to facilitate a coordinated communication approach. Moreover, EAGLE will foster a move towards the ideal of citizen-centred communication, including a participative component.The project will bring together representatives of nuclear actors, users of ionizing radiation, authorities, mass and social media, and informed civil society.
Agency: European Commission | Branch: FP7 | Program: CSA-CA | Phase: Fission-2013-6.0.1 | Award Amount: 1.22M | Year: 2013
The objective of PLATENSO is to provide a proposal towards establishing the legal base for a European Entity on Socio-Economic matters linked to nuclear technology and to develop recommendations for research strategies in PLATENSO countries. Thereby the capabilities of research institutes in Central and Eastern European countries to take part in EU research with respect to governance, social and societal aspects is enhanced. Initially, lessons learned from earlier projects, what is the state of knowledge in societal, social and governance issues, are reviewed and summarized. The research infrastructures within which project activities and future research are to take place are mapped and efforts are made to make sure research actors frame their approaches broad enough. Research strategies are formed for research in governance, social and societal issues in which participation in EU programmes is an integrated part. The strategies are tested with case studies to make sure they are feasible to implement. A number of networking activities are carried through as a major step toward actual foundation of the strategies in PLATENSO countries. In each country a PLATENSO partner will take responsibility for building a network of research institutions in its respective country. Establishment of the legal base for a European Entity on Socio-Economic matters linked to nuclear technology has potential to overcome the barriers that still exist for taking them fully into account and to make the awareness of the social and political challenges to come to action. On the basis of exploratory studies focusing on Central and Eastern Europe and contacts with relevant stakeholders in all EU, the project will analyze main aspects with regard to the implementation of the entity (organization, legal form, communication structure, content, etc.). Major areas on social, societal and governance issues for the envisaged Entity will be proposed. A nuclear energy scenario based on the Generation 4 ALLEGRO reactor concept will be given special attention as a pilot case for the European Entity giving support to ALLEGRO in social, societal and governance issues, which will include testing the draft strategy for research. The exact forms for this will be developed in close cooperation between PLATENSO and the ALLIANCE project.
Agency: European Commission | Branch: FP7 | Program: CP-IP | Phase: Fission-2011-2.3.1 | Award Amount: 9.69M | Year: 2012
Nuclear power issues have been attracting research interest for decades even since the actual use of power reactors using oxide fuels was considered a mature science. It has mainly been due to one of the great drawbacks of nuclear power, the waste handling. Presently, there is a renaissance in nuclear power research focused on a new generation of reactor concepts utilising more of the inherent energy of the fuels. Additionally, these new concepts will also produce less radioactive waste, which is radiotoxic for a shorter time frame. If such concept succeeds, nuclear power can be considered almost sustainable bearing in mind that the waste we already have generated may be used for next generations. In order to reach these goals, there are several issues to be considered and the future nuclear fuel is one of the most important ones. ASGARD project will conduct crosscutting studies in synergy with the current nuclear fuel and waste research projects in Europe (e.g. ACSEPT and FAIRFUELS projects), but will also extend further into the research on new innovative nuclear concepts (SFR-Prototype, MYRRHA). ASGARD will provide a structured R&D framework for developing compatible techniques for dissolution, reprocessing and manufacturing of new nuclear fuels. The fuels to be considered will mainly consist of the next generation of fuels, e.g. oxides, nitrides and carbides, since the current oxide fuels and their reprocessing is dealt within already existing projects. An educational programme will be implemented to share the knowledge between students, researchers in the fuel manufacturing and the fuel reprocessing communities. The challenging objectives of ASGARD will be addressed by a multi-disciplinary consortium composed of European universities, nuclear research bodies and major industrial stakeholders. ASGARD will be an essential contribution to the development of new sustainable nuclear fuel cycle concepts and thus pave the road to more sustainable nuclear future.
Agency: European Commission | Branch: FP7 | Program: CP | Phase: Fission-2012-2.3.1 | Award Amount: 10.27M | Year: 2013
Nuclear power plays a key role in limiting EUs greenhouse gases emissions, and makes an important contribution to improve European Unions independence, security and diversity of energy supply. However, its social acceptance is closely linked to an enhanced safety in the management of long-lived radioactive waste contributing to resource efficiency and cost-effectiveness of this energy and ensuring a robust and socially acceptable system of protection of man and environment. Among the different strategies, partitioning and transmutation (P&T) allows a reduction of the amount, the radiotoxicity and the thermal power of these wastes, leading to an optimal use of geological repository sites. In line with the Strategic Research Agenda of SNE-TP, the SACSESS collaborative project will provide a structured framework to enhance the fuel cycle safety associated to P&T. In addition, safety studies will be performed for each selected process to identify weak points to be studied further. These data will be integrated to optimise flowsheets and process operation conditions. A training and education programme will be implemented in close collaboration with other European initiatives, addressing safety issues of nuclear energy industry. The multidisciplinary consortium composed of European universities, nuclear research bodies, TSOs and industrial stakeholders will generate fundamental safety improvements on the future design of an Advanced Processing Unit. SACSESS will thus be an essential contribution to the demonstration of the potential benefits of actinide partitioning to the global safety of the long-lived waste management.
Agency: European Commission | Branch: FP7 | Program: CP-CSA | Phase: Fission-2012-4.2.1 | Award Amount: 5.40M | Year: 2013
Safety issues are of fundamental importance for the acceptance and sustainable application of nuclear energy. Actinides play a central role in the nuclear fuel cycle from mining, fuel fabrication, energy production, up to treatment of used fuel by reprocessing, partitioning and transmutation and/or finally management and disposal of radioactive waste. A fundamental understanding of actinide properties and behaviour in fuel materials, during the separation processes and once in geological repository is an imperative prerequisite to tackle all the related safety issues. Unravelling the complexity of the principal actinide components of used nuclear fuel certainly represents one of the grand challenges in nuclear science. In order to meet the needs of the safe and sustainable management of nuclear energy, it is therefore essential to maintain highest level of expertise in actinide sciences in Europe and to prepare the next generation of scientists and engineers who will contribute to develop safe actinide management strategies. Because actinides are radioactive elements, their study requires specific tools and facilities that are only available to a limited extent in Europe. Only a few academic and research organisations have the capabilities and licenses to work on these elements under safe conditions. It is therefore strategic to coordinate the existing actinide infrastructures in Europe, and to strengthen the community of European scientists working on actinides. In the continuation of ACTINET-6 and ACTINET-I3, TALISMAN will foster the networking between existing European infrastructures in actinide sciences open them widely to any European scientists by offering and supporting transnational access to unique facilities. To meet its objectives, TALISMAN will animate and organize a network of actinide facilities across the EU that will increase our knowledge for a safer management of actinides fostering training and education.
Instytut Chemii I Techniki Jadrowej | Date: 2014-02-05
The invention relates to the disposal of radioactive waste by a modified sol-gel method by enclosing it in durable ceramic crystallographic structures of ceramic synroc materials of type perovskite. The method according to the invention lies in the fact that to the previously prepared chlorine-free solution of colloidal sol, preferably Ti(NO_(3))_(4), the complexing compound is added, preferably ascorbic acid ASC, relative to the sum of the moles of metal from 0.1 to 0.3 and introduces calcium carbonate and elements included in the high-level radioactive waste, in the form of carbonates or nitrates, especially strontium, cobalt, cesium and neodymium, in a molar ratio of from 2% to 14% of the individual metals (Me), thereby replacing from 2% to 14% by mol of introduced Ca^(2+).The thus obtained sol is evaporated, dried and subjected to heat treatment and is eventually subjected to XRD and IR analysis, then the precursor of the synroc is pelletized and calcined at a temperature of 1200C for 2h.
Instytut Chemii I Techniki Jadrowej | Date: 2013-04-10
The subject of the invention is the way of selective separation of uranium and protactinium from irradiated in a nuclear reactor materials containing thorium. The method of selective extraction of uranium and protactinium from materials containing thorium, especially separating micro-amounts of uranium and protactinium from macro-amounts of other components containing thorium, especially ThO_(2), consists in dissolving a sample containing U, Th and Pa using a mixture of nitric acid, hydrofluoric acid and Al(NO_(3))_(3) in a hermetically closed vessel, made of polytetrafluoroethylene or derivatives of Teflon (PTFE, PFA). Next, the vessel is closed and heated in the temperature of 40-120C for minimum 1 hour, after which the obtained clear solution is put onto a chromatographic column, filled with trioctylphosphine oxide (TOPO) adsorbed on a hydrophobic sorbent, favourably polystyrene-divinylbenzene, and elution is conducted, favourably of 50 ml solution which is a mixture of nitric and hydrofluoric acids with an addition of aluminium nitrate (favourably THOREX) at the pace of 0.2-10 mL/300 s, while at the column, ^(233)Pa is quantitatively retained and the effluent from the column which contains Th and U is quantitatively moved to a vessel made of polytetrafluoroethylene or its analogues (PTFE or PFA) and evaporated to the volume of 0.5-5mL. Next, we add 0.5-5mL of H_(2)O, and next, the obtained solution is put onto the column, filled with quaternary aliphatic amine and conduct an elution with a solution which is a mixture of nitric and hydrofluoric acids with an addition of aluminium nitrate with H_(2)O, at the eluent flow rate of 0.2-10 mL/300 s, collecting fractions of volumes of 0.1-10mL, selectively separating U and Th. Uranium is eluted quantitatively in first five fractions, favourably four fractions (v=10 mL) and next, Thorium in fraction 7-25 (v=39 mL).
Instytut Chemii I Techniki Jadrowej | Date: 2013-07-24
According to the invention, the method of obtaining arsenic-72 radionuclide from selenium-72 radionuclide, consists in separating arsenic radionuclide from selenium radionuclide by the means of extraction chromatography, using hydrophobic styrene-divinylbenzene copolymers, especially Amberlite XAD-4 or Bio-Beads SM-2 carriers, with embedded substance, from the group of aromatic ortho-diamines, favourably 3,3 diaminobenzidine or 2,3 naphthalenediamine.The invention method, consists in placing 0.1-1 mL of Se-72 solution, containing selenium in the quartic level of oxidation on a glass column of 3-5 mm diameter and 35-55 mm height, containing sorbent with embedded, especially selected aromatic ortho-diamine, in the proportion of R-0.15, of grains diameter from 0.1 to 2 mm, and next, using 5 ml of hydrous solution of hydrochloric acid or sodium chloride, arsenic-72 radionuclide is eluted from the bed.According to the invention, the sorbent for obtaining arseninc-72 radionuclide, is characterised by the fact that it is a carrier in the form of hydrophobic styrene-divinylbenzene copolymer, favourably Amberlite XAD-4 or Bio-Beads SM-2 carrier, with embedded substance from the group including aromatic ortho-diamines, favourably 3,3 diaminobenzidine or 2,3 naphthalenediamine. According to the invention, the way of obtaining the sorbent for production of arsenic-72 radionuclide consists in mixing aromatic ortho-diamine pre-dissolved in hydrous-alcoholic solution, especially in the proportion 1:1, with an favourable carrier selected from the group of hydrophobic styrene-divinylbenzene copolymers, especially Amberlite XAD-4 or Bio-Beads SM-2, after which, the solvent is evaporated, favourably in the temperature of about 60C, stirring from time to time, until arid coloured sorbent is obtained.