Zhang C.-L.,GRS Society for plants and Reactor Safety
Journal of Rock Mechanics and Geotechnical Engineering | Year: 2013
The sealing behavior of fractures in clay rocks for deep disposal of radioactive waste has been comprehensively investigated at the GRS laboratory. Various sealing experiments were performed on strongly cracked samples of different sizes from the Callovo-Oxfordian argillite and the Opalinus clay under relevant repository conditions. The fractured samples were compacted and flowed through with gas or synthetic pore-water under confining stresses up to 18MPa and elevated temperatures from 20°C to 90°C. Sealing of fractures was quantified by measurements of their closure and permeability. Under the applied thermo-hydro-mechanical (THM) conditions, significant fracture closure and permeability decrease to very low levels of 10-19 to 10-21m2 were observed within time periods of months to years. The properties of the resealed claystones are comparable with those of the intact rock mass. All test results suggest high sealing potentials of the studied claystones. © 2013 Institute of Rock and Soil Mechanics, Chinese Academy of Sciences. Source
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: 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: 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.