Agency: Cordis | Branch: H2020 | Program: CSA | Phase: NFRP-05-2014 | Award Amount: 1.48M | Year: 2015
The coordination action SITEX-II aims at implementing in practice the activities along with the interaction modes issued by the FP7 program SITEX project (2012-2013), in view of developing an Expertise function network. This network is expected to ensure a sustainable capability of developing and coordinating joint and harmonized activities related to the independent technical expertise in the field of safety of deep geological disposal of radioactive waste. SITEX-II tasks include: the definition of the Strategic Research Agenda (SRA) based on the common R&D orientations defined by SITEX (2012-2013), the definition of the ToR for the implementation of specific topics from the SRA, and the interaction with IGD-TP and other external entities mandated to implement research on radioactive waste disposal regarding the potential setting up of an European Joint Programming on radioactive waste disposal; the production of a guidance on the technical review of the safety case at its different phases of development, fostering a common understanding on the interpretation and proper implementation of safety requirements for developing, operating and closing a geological repository and on the verification of compliance with these requirements; the development of a training module for generalist experts involved in the safety case review process, including the implementation a pilot training session; the commitment of CS in the definition of the SRA mentioned above, considering the expectations and technical questions to be considered when developing R&D for the purpose of Expertise function. Close interactions between experts conducting the review work will allow enhancing the safety culture of CS and more globally, proposing governance patterns with CS in the framework of geological disposal; the preparation of the administrative framework for a sustainable network, by addressing the legal, organisational and management aspects.
Agency: Cordis | Branch: H2020 | Program: RIA | Phase: NFRP-01-2014 | Award Amount: 6.64M | Year: 2015
The thermal-hydraulics Simulations and Experiments for the Safety Assessment of Metal cooled reactor (SESAME) project supports the development of European liquid metal cooled reactors (ASTRID, ALFRED, MYRRHA, SEALER). The project focusses on pre-normative, fundamental, safety-related, challenges for these reactors with the following objectives: Development and validation of advanced numerical approaches for the design and safety evaluation of advanced reactors; Achievement of a new or extended validation base by creation of new reference data; Establishment of best practice guidelines, Verification & Validation methodologies, and uncertainty quantification methods for liquid metal fast reactor thermal hydraulics. The SESAME project will improve the safety of liquid metal fast reactors by making available new safety related experimental results and improved numerical approaches. These will allow system designers to improve the safety relevant equipment leading to enhanced safety standards and culture. Due to the fundamental and generic nature of SESAME, developments will be of relevance also for the safety assessment of contemporary light water reactors. By extending the knowledge basis, SESAME will allow the EU member states to develop robust safety policies. At the same time, SESAME will maintain and further develop the European experimental facilities and numerical tools. The consortium of 25 partners provides American-European-wide scientific and technological excellence in liquid metal thermal hydraulics, as well as full alignment with ESNII and with NUGENIA where of interest. A close interaction with the European liquid metal cooled reactor design teams is foreseen involving them in the Senior Advisory Committee. They will actively advise on the content of the project and will be the prime end-users, ensuring their innovative reactor designs will reach highest safety standards using frontier scientific developments.
Agency: Cordis | Branch: FP7 | Program: CP | Phase: Fission-2012-2.1.2 | Award Amount: 6.27M | Year: 2013
The Fukushima accidents highlighted that both the in-depth understanding of such sequences and the development or improvement of adequate severe accident management measures is essential in order to further increase the safety of the nuclear power plants operated in Europe. CESAM (Code for European Severe Accident Management) is a R&D project that aims in particular at the improvement of the European reference code ASTEC towards a usage in severe accident management analysis for nuclear power plants (NPP). The models of ASTEC that are available for the relevant phenomena during severe accidents in the reactor core as well as in the spent fuel ponds are assessed and recommendations for improvement are developed. The lessons learned from the severe accident in Fukushima will be especially considered. Based on these recommendations ASTEC models will be improved and validated by the partners. In addition, ASTEC will be coupled to environmental consequences tools and a methodology will be investigated that evaluates the probability of different possible accident scenarios based on available on-side data during an accident in a nuclear power plant. This way, ASTEC will be extended to become a tool used for decision-making in emergency cases. ASTEC reference datasets for the main generic types of NPPs in Europe (PWR, BWR, CANDU) will jointly be prepared to give users appropriate guidance how to apply ASTEC for real plant analyses used e.g. for accident management. Plant analyses and possible improvements of SAM measures based on various plant scenarios and accounting for the lessons drawn from the Fukushima accidents, will be performed. A workshop will be organized to elaborate on ASTEC capabilities for calculations of the Fukushima accidents, both in the reactor core and the spent fuel ponds.
Agency: Cordis | Branch: FP7 | Program: CP-CSA | Phase: Fission-2013-2.1.1 | Award Amount: 10.28M | Year: 2013
Preparing NUGENIA for HORIZON 2020 The objective of the NUGENIA\ project is to support the NUGENIA Association in its role to coordinate and integrate European research on safety of the Gen II and III nuclear installations in order to better ensure their safe long term operation, integrating private and public efforts, and initiating international collaboration that will create added value in its activity fields. The project consists of two parts, the first part being a Coordination and Support Action and the second part a Collaborative Project. The aim of the first part, the Coordination and Support Action, is to establish an efficient, transparent and high quality management structure to carry out the planning and management of R&D including project calls, proposal evaluation, project follow-up dissemination and valorisation of R&D results in the area of safety of existing Gen II and future Gen III nuclear installations. The preparatory work will encompass governance, organizational, legal and financial work, as well as the establishment of annual work plans, with the aim to structure public-public and/or private-public joint programming enabling NUGENIA to develop into the integrator of the research in the respective field in Europe. The management structure will build on the existing organisation of the NUGENIA Association, currently grouping over 70 nuclear organisations from research and industry (utilities, vendors and small and medium enterprises) active in R&D. In the second part, the Collaborative project, one thematic call for research proposals will be organized among the technical areas of plant safety and risk assessment, severe accident prevention and management, core and reactor performance, integrity assessment of systems, structures and components, innovative Generation III design and harmonisation of procedures and methods. The call will take place one year after the start of the project. The call will implement the priorities recognised in the NUGENIA Roadmap, in line with the Sustainable Nuclear Energy Technology Platform (SNETP) and International Atomic Energy Agency (IAEA) strategies. The research call which is going to be organised within the project is open to all eligible organisations. The NUGENIA\ project will benefit from the experience of the NUGENIA Association member organisations on managing national research programmes and from the track record of the NUGENIA project portfolio.
Agency: Cordis | Branch: FP7 | Program: CP | Phase: Fission-2012-2.1.1 | Award Amount: 9.33M | Year: 2013
After the 2011 disaster that occurred in Japan, improvement of nuclear safety appears more clearly as a paramount condition for further development of nuclear industry. The NURESAFE project addresses engineering aspects of nuclear safety, especially those relative to design basis accidents (DBA). Although the Japanese event was a severe accident, in a process of defense-in-depth, prevention and control of DBA is obviously one of the priorities in the process of safety improvement. In this respect, the best simulation software are needed to justify the design of reactor protection systems and measures taken to prevent and control accidents. The NURESAFE project addresses safety of light water reactors which will represent the major part of fleets in the world along the whole 21st century. The first objective of NURESAFE is to deliver to European stakeholders a reliable software capacity usable for safety analysis needs and to develop a high level of expertise in the proper use of the most recent simulation tools. Nuclear reactor simulation tools are of course already widely used for this purpose but more accurate and predictive software including uncertainty assessment must allow to quantify the margins toward feared phenomena occurring during an accident and they must be able to model innovative and more complex design features. This software capacity will be based on the NURESIM simulation platform created during FP6 NURESIM project and developed during FP7 NURISP project which achieved its goal by making available an integrated set of software at the state of the art. The objectives under the work-program are to develop practical applications usable for safety analysis or operation and design and to expand the use of the NURESIM platform. Therefore, the NURESAFE project concentrates its activities on some safety relevant situation targets. The main outcome of NURESAFE will be the delivery of multiphysics and fully integrated applications.
Agency: Cordis | Branch: FP7 | Program: CP-CSA | Phase: Fission-2013-2.2.1 | Award Amount: 10.36M | Year: 2013
Preparing ESNII for HORIZON 2020 The aim of this cross-cutting project is to develop a broad strategic approach to advanced fission systems in Europe in support of the European Sustainable Industrial Initiative (ESNII) within the SET-Plan. The project aims to prepare ESNII structuration and deployment strategy, to ensure efficient European coordinated research on Reactor Safety for the next generation of nuclear installations, linked with SNETP SRA priorities. The ESNII\ project aims to define strategic orientations for the Horizon 2020 period, with a vision to 2050. To achieve the objectives of ESNII, the project will coordinate and support the preparatory phase of legal, administrative, financial and governance structuration, and ensure the review of the different advanced reactor solutions. The project will involve private and public stakeholders, including industry, research and academic communities, with opened door to international collaboration, involving TSO.
Agency: Cordis | Branch: FP7 | Program: CP | Phase: Fission-2013-1.1.2 | Award Amount: 14.73M | Year: 2013
The CAST project (CArbon-14 Source Term) aims to develop understanding of the generation and release of 14C from radioactive waste materials under conditions relevant to waste packaging and disposal to underground geological disposal facilities. The project will focus on releases from irradiated metals (steels, Zircaloys) and from ion-exchange materials as dissolved and gaseous species. A study to consider the current state of the art knowledge with regards to 14C release from irradiated graphite will also be undertaken, to further our knowledge from existing projects in this area i.e. CARBOWASTE. The scientific understanding obtained from these studies will then be considered in terms of national disposal programmes and impact on safety assessments. The knowledge gained from the whole of CAST will be disseminated within the project partners and to wider stakeholders and organisation, with a specific objective on education and training.
Agency: Cordis | Branch: FP7 | Program: CSA-CA | Phase: Fission-2013-4.1.1 | Award Amount: 3.41M | Year: 2013
The MYRRHA project aims to develop and to construct a world-class and first-of-a-kind nuclear research infrastructure. The design and the construction of the MYRRHA facility is particularly challenging since it requires the management of a large number of activities in view of achieving technical excellence in compliance with the project budget and schedule. Accordingly, state-of-the-art project management procedures and instruments have to be defined and implemented taking into account the constraints and the specifics of MYRRHA. The MARISA proposal for a Coordination and Support Action plans to bring the MYRRHA project to a level of maturity required to enable the construction work to start. Work proposed as part of MARISA includes the following main work packages: Overall coordination. In this work package, management procedures and instruments to oversee the overall coordination of the MYRRHA projects will be defined and developed. Strategic and consortium planning. As part of this work package, a roadmap will be developed for integrating different national and international initiatives in support of the MYRRHA development. Legal aspects. In the framework of the MARISA project, the appropriate legal framework for the MYRRHA undertaking will be identified and implemented. The legal framework will be tailored to the composition of the consortium and initiatives will be taken aiming at the implementation of inter-governmental agreements outlining participation in MYRRHA. Consortium governance. In this work package, appropriate management methods and procedures will be developed and implemented taking into account the particularity and the constraints of innovative projects as MYRRHA. Financial aspects. In this work package, cost specificities of the project and financing and funding mechanisms will be developed. Technical coordination work. The technical management of the MYRRHA project as part of MARISA involves coordination and support actions for
Agency: Cordis | Branch: H2020 | Program: RIA | Phase: NFRP-01-2014 | Award Amount: 8.21M | Year: 2015
The stabilization of molten corium is recognised as essential if a safe and stable state is to be reached following a severe accident. Among the possible options, In-Vessel Melt Retention (IVMR) appears as an attractive solution that would minimize the risks of containment failure (less Hydrogen produced, no corium-concrete interaction), if it can be proved to be feasible. The strategy is already adopted for the VVER 440 type 213 based on thorough research work for the Finnish Loviisa NPP and Hungarian Paks NPP. It is also included in the design of some new Gen.III reactors like AP-1000, APR 1400 and Chinese CPR-1000. It has also been studied in the past for other reactor concepts like KERENA (BWR) or VVER-640. Current approaches for reactors with relatively small power, such as VVER 440 or AP600, use conservative assumptions. However, for higher power reactors (around 1000 MWe), it is necessary to evaluate the IVMR strategy with best-estimate methods in order to address the uncertainties associated with the involved phenomena. Additional R&D is needed to ensure and demonstrate adequate safety margins, including identification of efficient technical solutions for the external cooling of the vessel and performing best-estimate evaluation of relevant scenarios. Among other provisions, the possibility of cooling the corium inside the vessel by direct injection of water into the degraded core, may be considered because it is likely to remove a significant part of the residual power. The goal of the project is an analysis of the applicability and technical feasibility of the IVMR strategy to high power reactors, both for existing ones (e.g. VVER 1000 type 320 units) as well as for future reactors of different types (PWR or BWR). The main outcomes of the project will be elevant assumptions and scenarios to estimate the maximum heat load on the vessel wall, improved numerical tools for the analysis of IVMR issues and a harmonized methodology on the IVMR.
Agency: Cordis | Branch: FP7 | Program: CP | Phase: Fission-2012-1.1.1 | Award Amount: 15.74M | Year: 2012
DOPAS aims to improve the adequacy and consistency regarding industrial feasibility of plugs and seals, the measurement of their characteristics, the control of their behavior over time in repository conditions and also their hydraulic performance acceptable with respect to the safety objectives. This DOPAS project addresses the design basis, reference designs and strategies to demonstrate the compliance of the reference designs to the design basis, for plugs and seals in geological disposal facilities. The project focuses on shaft seals for salt rock (German repository concept), tunnel plugs for clay rock (French and Swiss repository concepts), and tunnel plugs for crystalline rock (Czech, Finnish and Swedish repository concepts). Five different demonstration experiments are part of the project and will take place in Sweden, France, Finland, Czech Republic and Germany. They are in different state-of-development. The Swedish demonstrator will be constructed prior to start of the DOPAS project and will basically provide experience on demonstration of compliance of reference design to the design basis. German demonstrator will be installed after the DOPAS project and will focus on demonstration of suitability by performance assessment. The French, Finnish, Swedish,German and the Czech experiments will address developments in all phases of design basis, reference designs and strategies to demonstrate compliance of reference designs to design basis. The studied concepts will be developed in the DOPASs five thematic scientific/technological work packages, which each integrate the results of the individual experiments. The DOPAS project is derived from the IGD-TPs Strategic Research Agenda that points out the topic of plug and seals as a first priority issue for joint European RTD projects.