Nuclear Research and Consultancy Group is a Dutch institute that performs nuclear research for the government and private companies. It is the most important producer of radionuclides in Europe and maintains and operates the Petten nuclear reactor.The institute also offers services to medical, chemical, oil, and gas companies. Wikipedia.
Agency: Cordis | Branch: H2020 | Program: RIA | Phase: NFRP-06-2014 | Award Amount: 9.66M | Year: 2015
The Modern2020 project aims at providing the means for developing and implementing an effective and efficient repository operational monitoring programme, taking into account the requirements of specific national programmes. The work allows advanced national radioactive waste disposal programmes to design monitoring systems suitable for deployment when repositories start operating in the next decade and supports less developed programmes and other stakeholders by illustrating how the national context can be taken into account in designing dedicated monitoring programmes tailored to their national needs. The work is established to understand what should be monitored within the frame of the wider safety cases and to provide methodology on how monitoring information can be used to support decision making and to plan for responding to monitoring results. Research and development work aims to improve and develop innovative repository monitoring techniques (wireless data transmission, alternative power supply sources, new sensors, geophysical methods) from the proof of feasibility stage to the technology development and demonstration phase. Innovative technical solutions facilitate the integration and flexibility of required monitoring components to ease the final implementation and adaptation of the monitoring system. Full-scale in-situ demonstrations of innovative monitoring techniques will further enhance the knowledge on the operational implementation of specific disposal monitoring and will demonstrate the performance of the state-of-the-art, the innovative techniques and their comparison with conventional ones. Finally, Modern2020 has the ambition to effectively engage local citizen stakeholders in the R&D monitoring activity by involving them at an early stage in a repository development programme in order to integrate their concerns and expectations into monitoring programmes.
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-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-2013-5.1.1 | Award Amount: 1.50M | Year: 2014
For a vast amount of applications in the medical, industrial, research and other sectors, a good understanding of radiation protection (RP) is fundamental in order to protect workers, the public and the environment from the potential risks of ionising radiation. Within this perspective, building and maintaining an advanced level of competence in RP, assuring sufficient well-trained personnel and organising an adequate knowledge management, is crucial. Effective education and training (E&T) is a critical element in these matters, helping to prevent the decline in expertise and to meet future demands. ENETRAP III adds new and innovative topics to existing E&T approaches in RP. It will further develop the European reference training scheme with additional specialized modules for Radiation Protection Experts working in medical, waste management and NPP. It will implement the ECVET principles and will establish targeted assistance from regulators that will play a crucial role in the endorsement of the proposed courses and learning objectives. ENETRAP III will also introduce a train-the-trainer strategy. All organised pilot sessions will be open to young and more experienced students and professionals. In this way, ENETRAP III aims to contribute to increasing the attractiveness of nuclear careers and to lifelong learning activities. A web-based platform containing all relevant information about E&T in RP will facilitate an efficient knowledge transfer and capacity building in Europe and beyond. ENETRAP III will also propose guidance for implementing E&T for Radiation Protection Experts and Officers, hereby providing extremely important assistance to all Member States who are expected to transpose the Euratom BSS requirements into their national legislations. Moreover, ENETRAP III will demonstrate the practical feasibility of earlier developed concepts for mutual recognition and thus provide leading examples in Europe demonstrating effective borderless mobility.
Agency: Cordis | Branch: H2020 | Program: RIA | Phase: NFRP-06-2014 | Award Amount: 5.95M | Year: 2015
The HORIZON 2020 EURATOM Collaborative Project Cement-based materials, properties, evolution, barrier functions (Cebama) is developed with the overall objective to support implementation of geological disposal of nuclear waste by improving the knowledge base for the Safety Case. Cement-based materials are highly relevant in this context, being used as waste forms, liners and structural components or sealing materials in different types of host rocks and disposal concepts. Specific objectives of Cebama are (i) experimental studies of interface processes between cement based materials and host rocks or bentonite, and assessing the specific impact on transport properties, (ii) quantifying radionuclide retention under high pH cement conditions, and (iii) developing comprehensive modeling approaches. Modeling will support interpretation of results and prediction of the long-term evolution of key transport characteristics such as porosity, permeability and diffusion parameters especially in the interface between cement based materials and the engineered and natural barriers. Further objectives cover dissemination of results to scientific and non-scientific stakeholders as well as training and education of young professionals for carrying over the expertise into future implementation programms. To a large extent, the experimental and modelling work will be part of PhD theses, aiming at high scientific-technical impact and quality with respect to peer-reviewed publications. The 4 years project is implemented by a consortium of 27 partners consisting of large Research Institutions, Universities, one TSO and one SME from 9 EURATOM Signatory States, Switzerland and Japan. National Waste Management Organizations support Cebama by co-developing the work plan, participation in the End-User Group, granting co-funding to some beneficiaries, and providing for knowledge and information transfer.
Agency: Cordis | Branch: H2020 | Program: RIA | Phase: NFRP-09-2015 | Award Amount: 11.99M | Year: 2015
The Strategic Research Agenda of the EU Sustainable Nuclear Energy Technical platform requires new large infrastructures for its successful deployment. MYRRHA has been identified as a long term supporting research facility for all ESNII systems and as such put in the high-priority list of ESFRI. The goal of MYRTE is to perform the necessary research in order to demonstrate the feasibility of transmutation of high-level waste at industrial scale through the development of the MYRRHA research facility. Within MYRRHA as a large research facility, the demonstration of the technological performance of transmutation will be combined with the use for the production of radio-isotopes and as a material testing for nuclear fission and fusion applications. Numerical studies and experimental facilities are foreseen to reach this goal. Besides coordination, international collaboration and dissemination activities, the MYRTE proposal contains 5 technical work packages. The first and largest work-package is devoted to the realisation of the injector part of the MYRRHA accelerator to demonstrate the feasibility and required reliability of this non-semi-conducting part of the accelerator. The second work-package addresses the main outstanding technical issues in thermal hydraulics by numerical simulations and experimental validation. Pool thermal hydraulics and thermal hydraulics of the fuel assembly will be the focus of this WP. In the WP on LBE Chemistry, the evaporation from LBE, capture and deposition of Po and fission products will be studied in detail to complement the safety report. A small dedicated WP on experimental reactor physics is also foreseen to allow carrying out the necessary supplementary experiments at the GUINEVERE-facility to address the questions of the safety authorities. In a last WP, advanced studies on Americium-bearing oxide fuel are carried out to demonstrate the capability of developing minor actinide fuel for transmutation.
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.