CAST: CArbon-14 Source Term
The CAST project (CArbon-14 Source Term) aimed to develop understanding of the potential release mechanisms of carbon-14 from radioactive waste materials under conditions relevant to waste packaging and disposal in underground geological disposal facilities.
Overview
Project Dates: 1/10/2013 – 31/03/2018
Project Status: Finished
Project Website: www.projectcast.eu
In our atmosphere, carbon-14 is continuously generated from nitrogen (about 80% of air) and is incorporated into all living things. When a species dies, the incorporation of this cosmogenically generated carbon-14 stops and its content decreases by radioactive decay. The degree of carbon-14 decay in material from once living things allows archaeologists to determine how old their findings of biological origin (e.g. a wooden tool) are. Carbon-14 is also generated in nuclear reactors, for example, during irradiation of metals containing nitrogen or carbon additions. These materials are considered radioactive waste for which special safety measures are and will be taken. The CAST project (CArbon-14 Source Term) aimed to develop understanding of the potential release mechanisms of carbon-14 from radioactive waste materials under conditions relevant to waste packaging and disposal in underground geological disposal facilities. The expected increase in understanding should decrease uncertainties in the long-term safety assessment and increase confidence in the safety case.
The CAST consortium brought together 33 partners with many different skills and competences both in geological disposal of difference waste types, but also in developing safety cases and on planning and implementing experimental programmes on gas generation. The consortium included national waste management organisations, research institutes, universities and commercial organisations working in this field. The involvement of the waste management organisations (the end-users of the outcome in the form of process understanding, data and competence) ensured that the project focused on important and outstanding issues. It also ensured that the project aligned to European national programmes and thus that results are used as intended. Two partners were from outside Europe – one from the Ukraine (SI IEG NASU) and one from Japan (RWMC). This offered a unique extension of scientific basis to the project, as well as an insight into how other national programmes manage the issue of carbon-14.
CAST was a collaborative project that received funding from the European Union’s Seventh Framework Programme for research, technological development and demonstration.
Objective
The scope of CAST was defined through a process of consultation initiated by a questionnaire circulated to a wide range of organisations. A synthesis of the responses to the questionnaire showed that carbon-14 release from irradiated steels, Zircaloys, graphites and from ion-exchange resins were of widest interest. The responses indicated that there were several on-going (or planned studies) on irradiated graphites and uncertainties on carbon-14 release rates and speciation remain to be resolved. However, there was less on-going work and little information available for the release of carbon-14 from irradiated steels, Zircaloys and ion-exchange resins.
Therefore, the objectives of CAST were to:
- gain a scientific understanding of the carbon-14 release mechanisms and rates from the corrosion of irradiated steels and Zircaloys and from the leaching of ion-exchange resins and irradiated graphites under geological disposal conditions;
- provide speciation of the carbon-14 release and how this relates to aqueous conditions;
- evaluate this understanding in the context of national safety assessments; and
- disseminate this understanding and its relevance to safety assessments to a range of interested stakeholders and provide an opportunity for training of early career researchers.
These objectives address Topic 2 in Key Topic 2 (Understanding the Wastes) of the IGD-TP Strategic Research Agenda, which identifies a need for improved data and understanding of the underpinning scientific mechanisms of the release of radionuclides and chemical species from various long-lived Intermediate Level Wastes. This includes detailed characterisation methods, issues related to adequate inventory determinations, chemical form, speciation on release and transport in the near field and far field.
Programme
Data for rates of release of carbon-14 and its speciation are sparse. Therefore, in safety assessments it is often assumed that carbon-14 is released from irradiated metals in a single chemical form at a rate dependent on the corrosion rate of the metal and the inventory of carbon-14. Similarly, estimates of the rate of release from irradiated graphite may be based on simple assumptions about the proportion of the carbon-14 that is ‘labile’ and on short-term leaching results. CAST investigated the release of carbon-14 from irradiated steels, irradiated Zircaloys, spent ion exchange resins (IEX) and irradiated graphites. A work package was devoted to each type of material in which fundamental scientific experiments will be performed and conceptual models for carbon-14 release were developed. CAST aimed to provide a significant advance on the current understanding by obtaining direct experimental data for the rates of release of carbon-14 from these waste components, rather than relying on hypotheses based on assumptions about speciation and distribution and extrapolation from corrosion rate data that may be around the limit of detection.
The impact of the results of CAST on the safety arguments and assessments of geological disposal across a range of concepts was considered through a specific work package: Safety case relevance. This enabled key messages on repository design and future R&D requirements to be developed without risk of a narrow focus. CAST took into account information from relevant existing studies, including those carried out as part of CARBOWASTE and FORGE, in developing these key messages.
The CAST project was carried out in seven Work Packages (WPs).
WP1 Co-ordination
The main objectives for WP1 co-ordination were:
- to manage and coordinate the project and provide support to the different work packages;
- to advise and support the work package leaders in the work package planning;
- to assist WP7 with the public information to be shared on the CAST website;
- to collect and compile project management information for the project to ensure compliance with the requirements set out in the consortia agreement and the EC Grant agreement;
- to organise the distribution of EC financial contributions and collection of audit certificates; and
- to provide a means of quality assurance and control of project results.
WP Steels
The main objectives for WP2 Steels were:
- to develop analytical techniques for identification and quantification of 14C species formed during corrosion of irradiated steels under conditions relevant to cement-based repositories;
- to validate existing activation models by measuring 14C inventories in irradiated steel;
- to carry out experiments and modelling to further our understanding of the speciation and rate of 12C/13C and 14C release from corrosion of irradiated and unirradiated steels under conditions relevant to deep geological repositories; and
- to incorporate information from existing and on-going projects elsewhere on steel corrosion into this work package, to make the current understanding available.
WP3 Zircaloy
The objective of WP3 Zircaloy was to obtain a better understanding of 14C behaviour in waste Zr fuel claddings under disposal conditions with regard to 14C inventory (and origins), release from waste packages and speciation of released 14C. This was achieved by:
- assessing 14C inventories in zirconium alloy metals and oxides;
- characterising 14C release from Zr corrosion and Zr oxide dissolution determining 14C speciation under simulated disposal conditions.
WP4 Ion Exchange Resins
The objective of WP4 Ion Exchange Resins was to obtain a better understanding of the 14C source term from spent ion-exchange resins of Boiling and Pressurized Water Reactors under different storage strategies and likely release and chemical species under geological disposal conditions. This will be achieved by reviewing the current status of understanding, characterising the 14C inventory and its speciation and undertaking experiments to measure 14C release to gas and solution and its speciation.
WP5 Graphite
The objective of WP5 Graphite was to understand the factors determining release of 14C from irradiated graphite (i-graphite) under geological disposal conditions. This was achieved through:
- determining the 14C inventory and concentration distribution in i-graphites and factors that may control these;
- measuring the rate and speciation of 14C release to solution and gas from i-graphites in contact with aqueous solutions; and
- determining the impact of selected waste treatment options on 14C release and relating this to the nature of 14C in i-graphite.
WP6 Safety Case Relevance
WP6 Safety case relevance regrouped the Waste Management Organisations (WMOs) participating in CAST with the aim of:
- combining the results of WP 2 – 5 to deliver sound scientific basis and safety relevant information;
- considering the CAST results in the context of safety cases;
- identifying commonalities and differences between national programmes and;
- providing conclusions and recommendations over possible future studies and orientations to waste management organisations. WP6 acted as an integration exercise to ensure that the results from WP2 to 5 are as relevant to the safety cases for the end-users, the WMOs, as possible.
WP7 Dissemination
The objectives of WP7 Dissemination were to disseminate information about CAST activities and results (provided they are suitable for public circulation) as widely as possible to various target groups having an interest in the project and its results. For public dissemination, workshops were held for waste management organisations, regulators and waste generators. Information has been provided in reports, presentations in scientific fora, scientific publications and newsletters for laypeople. There were also training courses to actively train early-career participants in CAST activities.
Funding Bodies
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European Union
CAST has received funding from the European Union’s Seventh Framework Programme for research, technological development and demonstration under grant agreement number 604779. The total budget was 14.73 million Euros, with the EU contributing 4.51 million Euros. Further information is available at http://cordis.europa.eu/project/rcn/110253_en.html
Related Documents
CAST Final General Assembly – Third announcement and call for papers
Description: Third announcement and call for papers for the CAST final general assembly in Lyon, France, on 16-18 January 2018.
Last updated: October 20, 2017
CAST 2014 D3.1 State of the art of 14C in Zircaloy and Zr alloys
Description: CAST - This report provides a review of the current status of knowledge on various aspects related to the release of 14C from zirconium alloys waste (hulls), which is of importance for long-term safety analyses of final repositories for long-lived Intermediate level waste.
Last updated: September 23, 2014
CAST 2015 D4.1 State of art review of spent ion exchange resins
Description: CAST - A state of the art review on the different techniques used to characterize spent ion exchange resins is presented. A large part of the works that were done so far are based on liquid scintillation counting, but an increasing amount of determination are now performed in accelerator mass spectrometry. Other non-conventional techniques are also reviewed. Finally, a status of knowledge is provided on the possible chemical forms (speciation) under which 14C can be released from spent ion exchange resins. Analytical strategies for speciation by partners are also described. Available estimations of the proportion of inorganic vs. organic forms are reviewed as well as the possibility of the different forms of organic molecules, and gaseous release.
Last updated: February 23, 2015
CAST 2015 D2.1 State of the art review of steel corrosion and C14 release
Description: CAST - The objective of this report is to review the current state of understanding of steel corrosion rates and carbon-14 releases from irradiated steels under conditions relevant to the storage and long-term disposal of radioactive wastes and thereby incorporate information available from outside the CAST project into CAST WP2.
Last updated: February 23, 2015
CAST 2015 D3.6 Intermediate report on the analysis of samples total C14 content
Description: CAST - D3.6 forms part of CAST task 3.3 “Characterisation of C-14 released from irradiated Zirconium fuel clad wastes”. This report summarises the progress at ITU to the end of March 2015.
Last updated: June 23, 2015
Description: CAST - To ensure knowledge and understanding from the CARBOWASTE project is thoroughly considered in the CAST project, Task 5.1 is being undertaken in the first year of CAST. This task is the subject of the current report, and has the aim to review CARBOWASTE and other relevant R&D activities to establish the current understanding of inventory and release of carbon-14 from irradiated graphites.
Last updated: July 23, 2015
CAST 2016 D6.1 C14 in safety assessments
Description: CAST - The first phase of WP6, prior the analysis of the experimental results delivered by the project, aims at taking stock of the C-14 knowledge from the angle of safety assessments. Deliverable D6.1 gives an overview on this for each national program. On the basis of this compilation, commonalities and differences between disposal concepts regarding the impact of the uncertainties linked to C-14 release from radioactive waste disposal will be identified as well as the way to cope with them. This thorough discussion will be the object of deliverable D6.2.
Last updated: January 23, 2016
CAST 2016 D5.3 Reports on graphite categories in the RBMK reactor
Description: CAST - This report presents information on graphite characterisation as is being undertaken as part of the Chernobyl Nuclear Power Plant Decommissioning Program. Work considering chemical decontamination of graphite is reported, as is the overall graphite waste management approach.
Last updated: March 23, 2016
CAST 2016 D5.8 Synthesis report on 14C speciation in solution and gas from French graphite waste
Description: CAST - Carbon 14 is one of the key radionuclides for the future disposal of French irradiated graphite waste. It is one of the main long-lived radionuclides, and depending on its speciation, it can be more or less mobile in a disposal facility and more or less incorporated into living organisms. Following a first report concerning a review of the available leaching data of French irradiated graphite, particularly focused on carbon 14 release rates (D5.1), this second report (D5.8) addresses the speciation of the released carbon 14.
Last updated: April 23, 2016
CAST 2016 D5.7 Report on C14 distribution in irradiated graphite from research reactor VVR-S
Description: CAST - The main objective of the IFIN-HH in the second year of its input to Work Package 5 was to update the inventory of 14C in the irradiated graphite arising from thermal column of VVR-S Reactor and radioactive wastes containing organic and inorganic 14C compounds. IFIN-HH has characterized the 14C inventory of irradiated graphite from thermal column of VVR-S Reactor, and has started to develop a method, based on the use Accelerator Mass Spectrometry (AMS) which will be suitable to characterize the distributions of14C inventory in irradiated graphite. Finally, in order to measure the total release of 14C (and 3H) to solution and gas from crushed and intact i-graphite from the VVR-S Reactor, the experimental apparatus has been designed and manufactured.
Last updated: July 23, 2016
CAST 2017 D3.9 Quantification of C14 in liquid and gas
Description: CAST - This report presents the work developed by SUBATECH, CEA and RWMC.
Last updated: March 23, 2017
CAST 2017 D7.11 Proceedings of the First Workshop
Description: CAST - The 1st Workshop of the CAST project was held 5 - 6 October 2016 at the COVRA facilities, Vlissingen, Netherlands. Presentations were given showing the status of project work and scientific-technical achievements, but also how the project work falls in the wider context. A series of topics were identified where R&D is still required in order to obtain the desired confidence in safety for geological disposal of the concerned waste materials. This is also relevant for the question to which extent confidence in safety for disposal in less ambitious facilities than deep geological ones can be justified, with or without pre-treatment of the waste material.
Last updated: March 23, 2017
CAST 2017 D2.7 Report on C14 release speciation from carbon steel under alkaline reducing conditions
Description: CAST - The aim of the work at SCK•CEN in the framework of Work Package 2 of the CAST project was to investigate the release of 14C from carbon steels representative for the reactor pressure vessel (RPV) steel of Belgian nuclear power plants and the 14C speciation in a cementitious environment, which is relevant for the Belgian geological disposal concept, which involves placing the RPV steel in a concrete monolith.
Last updated: July 23, 2017
CAST 2017 D2.11 Report on C14 release speciation from stainless steel under acidic conditions
Description: CAST - In this report the work performed by the Karlsruhe Institute of Technology (KIT) with support from the National Cooperative for the Disposal of Radioactive Waste (NAGRA, Switzerland) within the work package 2 of the CAST project is summarized. In the following sections, the thermodynamic modelling of 14C in metals is presented as well as the experimentally determined 14C inventory in irradiated steel and the chemical form of 14C released from the studied material.
Last updated: July 23, 2017
CAST 2017 D2.12 Report on C14 release speciation from stainless steel
Description: CAST - RWMC has studied the aqueous corrosion of non-irradiated stainless steel under simulated repository conditions.
Last updated: July 23, 2017
CAST 2017 D5.11 Report on exfoliation processes and on structural and morphological properties
Description: CAST - In this deliverable, the behaviour of nuclear graphite through the exfoliation process has been studied, carried out with different organic solvents to remove primarily radiocarbon and estimate the “Removal Efficiency“ (as percentage of the recovered activities after treatment in comparison to the original values) of the used solvents in order to propose a reliable approach to produce graphite for recycling or/and safety disposed as L&ILW.
Last updated: July 23, 2017
CAST 2017 D5.17 Report on modelling of 14C inventory in RBMK reactor core
Description: CAST - This report is one of the CAST Work Package 5 (WP5) deliverables and it presents results of Lithuanian Energy Institute (LEI) activities performed in the Task 5.2 “Characterisation of the C-14 inventory in i-graphites”.
Last updated: July 23, 2017
CAST 2017 D6.2 Knowledge supporting safety assessments of 14C
Description: CAST - Work Package 6 of the CAST project is devoted to the knowledge base concerning the re-lease and transport of 14C in the context of post-closure safety assessments of the geological disposal of radioactive waste. This report (D6.2) assesses the various approaches for safety assessment discussed in report D6.1 in the light of the existing knowledge about the 14C source term. It proposes a synthesis of D6.1, identifies commonalities and differences between approaches and concepts and highlights safety-critical uncertainties pertaining to 14C fate in waste disposal.
Last updated: July 23, 2017
CAST 2017 D5.14 Release of C14 from irradiated VVR-S graphite to solution and gas phases
Description: CAST - Irradiated graphite, dismantled from the thermal column of VVR-S Reactor, contains different radioisotopes as activation products, including carbon-14 (C-14) and tritium (H-3). In repository-relevant conditions, this graphite could be a source of gases containing C-14 and H-3. In the experiments performed by IFIN-HH we have investigated the release of C-14 and H-3 from two intact samples of irradiated graphite which have been cut from the thermal column disc located near the reactor core.
Last updated: August 23, 2017
CAST 2017 D5.15 Final report on 14C leaching from Vandellos graphite
Description: CAST - The development of both analytical methods and protocols to measure the release of 14C from irradiated graphite samples and the speciation in the aqueous and gaseous phase has been performed throughout the CAST project. Analytical methods, suited to identify and quantify low molecular weight organic molecules, comprise Ion Exchange Chromatography and Gas Chromatography coupled to Mass Spectrometry, they are described for aqueous and gaseous samples. Also, the preparation of the leaching experiments to measure the release of 14C is described in this report.
Last updated: August 23, 2017
CAST 2017 D5.12 Final evaluation of leach rates of treated and untreated i-graphites
Description: CAST - Work Package 5 of the EC CAST project considers the behaviour of 14C i-graphite. In particular, the work is focused on understanding the factors determining the release of 14C from irradiated graphite (hereafter “i-graphite") under disposal conditions (including surface disposal facilities and deep geological disposal facilities). In this study, the release of 14C was investigated in model experiments with i-graphite from the Rossendorf Research Reactor (RFR).
Last updated: September 23, 2017
CAST 2017 D5.18 Report on 13C behaviour under ion irradiation in HOPG model (model graphite)
Description: CAST - The aim of work undertaken by IPNL is to simulate the behaviour of 14C during reactor operation and evaluate the independent or synergistic effects of temperature and irradiation on 14C behaviour.
Last updated: September 23, 2017
Description: CAST - This report is deliverable D2.8 of the CAST project. In this deliverable, the details about the experiments focusing on the study of C-14 release form irradiated steel are presented. It includes the samples, experiment design, description of analytical methods, experiment and its results, and discussions of the results. This deliverable describes results up to 5 months of running the experiment.
Last updated: October 23, 2017
CAST 2017 D7.9 All course notes for training course 1
Description: CAST - This report contains the presentations made at Training Course 1 of CAST held on 5th and 6th July 2016 at Karlsruhe Institute of Technology.
Last updated: June 23, 2017
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CAST 2016 D7.11 Proceedings of Workshop 1, 5-6 October 2016
Description: CAST - This report is deliverable D7.11 of the CAST project, detailing the proceedings of workshop 1 held on 5-6 October 2016.
Last updated: December 20, 2017
CAST 2018 WP2 Steels Deliverables
Description: Zip file of all publicly available deliverables from the CAST project produced under Work Package 2: Steels.
Last updated: September 27, 2018
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CAST 2018 WP3 Zircaloy Deliverables
Description: Zip file of all publicly available deliverables from the CAST project produced under Work Package 3: Zircaloy.
Last updated: September 27, 2018
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CAST 2018 WP4 Ion Exchange Resins Deliverables
Description: Zip file of all publicly available deliverables from the CAST project produced under Work Package 4: Ion Exchange Resins.
Last updated: September 27, 2018
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CAST 2018 WP5 Graphite Deliverables
Description: Zip file of all publicly available deliverables from the CAST project produced under Work Package 5: Graphite.
Last updated: September 27, 2018
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CAST 2018 WP6 Safety Case Relevance Deliverables
Description: Zip file of all publicly available deliverables from the CAST project produced under Work Package 6: Safety Case Relevance.
Last updated: September 27, 2018
CAST 2018 D7.20 Workshop 2 Report
Description: CAST deliverable D7.20, report of workshop 2.
Last updated: September 27, 2018
Description: CAST deliverable D7.22, newsletter 5.
Last updated: September 27, 2018
CAST 2018 D7.23 Final Overview of CAST
Description: CAST deliverable D7.23, Final Overview of CAST.
Last updated: September 27, 2018
CAST 2018 D7.24 Summary of Scientific Progress Achieved
Description: CAST deliverable D7.24, Summary of Scientific Progress Achieved Through CAST.
Last updated: September 27, 2018
CAST 2018 D7.25 Summary of Scientific Progress Achieved- For Public and Decision-makers
Description: CAST deliverable D7.25, Summary of Scientific Progress Achieved Through CAST for the general public and decision-makers.
Last updated: September 27, 2018
Last updated: August 22, 2019
Last updated: August 22, 2019
Last updated: August 22, 2019
Last updated: August 22, 2019
CAST Deliverable D1.10 – Advisory Group Review of WP 2 Final Synthesis Report
Last updated: August 22, 2019
CAST Deliverable D1.11 – Advisory Group Review of WP 3 Final Synthesis Report
Last updated: August 22, 2019
CAST Deliverable D1.12 – Advisory Group Review of WP 4 Final Synthesis Report
Last updated: August 22, 2019
CAST Deliverable D1.13 – Advisory Group Review of WP 5 Final Synthesis Report
Last updated: August 22, 2019
CAST Deliverable D1.14 – Advisory Group Review of WP6 Final Synthesis Report
Last updated: August 22, 2019
CAST Deliverable D1.16 – Advisory Group Review of 2018 GAM and Final Symposium
Last updated: August 22, 2019
CAST Deliverable D1.17 – Advisory Group Review of WP7 CAST Final Overview Report
Last updated: August 22, 2019
CAST Deliverable D2.4 – Selected analytical procedures at Armines/Subatech
Last updated: August 22, 2019
CAST Deliverable D2.6 – WP2 Annual Progress Report – Year 3, October 2015 – September 2016
Last updated: August 22, 2019
CAST Deliverable D2.10 – Determination of 14C Content and Release from Steel
Last updated: August 22, 2019
CAST Deliverable D2.13 – WP2 CIEMAT Final Report on C14 release from steels under aerobic conditions
Last updated: August 22, 2019
CAST Deliverable D2.14 – WP2 ENRESA Final Report on C14 release from steels under aerobic conditions
Last updated: August 22, 2019
CAST Deliverable D2.15 – Influence of material choice on the release and speciation of C14
Last updated: August 22, 2019
CAST Deliverable D2.16 – Final report on C-14 release from steels under low pH and acidic conditions
Last updated: August 22, 2019
Last updated: August 22, 2019
Last updated: August 23, 2019
Last updated: August 23, 2019
Last updated: August 23, 2019
CAST Deliverable D3.4 – Progress report on corrosion tests in the hot cell-experimental setup
Last updated: August 23, 2019
CAST Deliverable D3.6 – Intermediate report on the analysis of Zircaloy samples C-14 content
Last updated: August 23, 2019
CAST Deliverable D3.7 – Definition of the analytical strategy for C-14 measurements
Last updated: August 23, 2019
CAST Deliverable D3.8 – Description of Zircaloy-4 dissolution experiment in a shielded box
Last updated: August 23, 2019
CAST Deliverable D3.9 – Quantification of C-14 in liquid and gas phases
Last updated: August 23, 2019
CAST Deliverable D3.15 – Final report on C14 release and speciation from Zircaloy
Last updated: August 23, 2019
Last updated: August 23, 2019
CAST Deliverable D3.19 – Final Report on Zr alloys corrosion studies at RWMC
Last updated: August 23, 2019
Last updated: August 23, 2019
Last updated: August 23, 2019
Last updated: August 23, 2019
CAST Deliverable D4.8 – Compilation and comparison of data on C14 from spent ion-exchange resins
Last updated: August 23, 2019
Last updated: August 23, 2019
IGD-TP Members Participating in the Activity
Nuclear Waste Services (NWS) [Previously RWM]
Member of Executive Group
Nuclear Waste Services (changed from Radioactive Waste Management Limited in 2022)
Contact: Jonathan Martin Send message
VTT Technical Research Centre of Finland
Contact: Erika Holt Send message
Nagra
Member of Executive Group
Nationale Genossenschaft für die Lagerung radioaktiver Abfälle
Contact: Irina Gaus Send message
ANDRA
Member of Executive Group
Agence Nationale pour la gestion des déchets radioactifs
The French National Radioactive Waste Management Agency.
Contact: Stephan Schumacher Send message
Nuclear Research Institute Rez (UJV)
Contact: Vaclava Havlova Send message
ONDRAF/NIRAS
Member of Executive Group
The Belgian Agency for Radioactive Waste and Enriched Fissile Materials
Contact: Maarten Van Geet Send message
COVRA
Member of Executive Group
Centrale Organisatie Voor Radioactief Afval
Contact: Ewoud Verhoef Send message
Le Commissariat à l’énergie atomique et aux énergies alternatives (CEA)
French Alternative Energies and Atomic Energy Commission
Contact: Catherine Rabbe Send message
Laboratory for Waste Management (LES)/Paul Scherrer Institute (PSI)
Contact: Sergey Churakov Send message
SCK – CEN
Belgian Nuclear Research Centre
Contact: Christophe Bruggeman Send message
Karlsruhe Institute of Technology (KIT)
Contact: Horst Geckeis Send message
ENEA
Agenzia Nationale per le nuove tecnologie, lénergia e lo sviluppo economico sostenible
Italian National Agency for New Technologies, Energy and Sustainable Economic Development.
Contact: Alfredo Luce Send message
Radioactive Waste Management Funding and Research Center (RWMC)
Radioactive Waste Management Funding and Research Center
Contact: Hirmoi Tanabe Send message
Contact: Tomofumi Sakuragi Send message
Contact: Hidekazu Asano Send message
Contact: Jiro Eto Send message
Forschungszentrum Jülich
Contact: Dirk Bosbach Send message
ENRESA
Member of Executive Group
Empresa Nacional de Residuos Radioactivos S.A.
Contact: Mariano Navarro Send message
Contact: Juan-Carlos Major Send message
Lithuanian Energy Institute (LEI)
Contact: Povilas Poškas Send message
Nuclear Research and Consultancy Group (NRG)
Contact: Arjen Poley Send message
SÚRAO
Member of Executive Group
Správa úložišť radioaktivních odpadů
Radioactive Waste Repository Authority, Czechia
Contact: Lukáš Vondrovic Send message
Contact: Markéta Dohnálková Send message
Svensk Kärnbränslehantering AB (SKB)
Member of Executive Group
Svensk Kärnbränslehantering AB
Swedish Nuclear Fuel and Waste Management Co.
Contact: Björn Herschend Send message
Centre National de la Recherche Scientifique (CNRS)
The National Center for Scientific Research, France
Contact: Michel Cathelineau Send message
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT)
Center for Energy, Environmental and Technological Research
Contact: Tiziana Missana Send message
Orano Group
Contact: Magali Smets Send message
Gesellschaft für Anlagen- und Reaktorsicherheit mbH (GRS)
Contact: Tilmann Rothfuchs Send message
Contact: Klaus Fischer-Appelt Send message
European Commission, Joint Research Center (JRC), Institute for Transuranium
The mission of the JRC Institute for Transuranium Elements (JRC-ITU) is to provide the scientific foundation for the protection of European citizens against risks associated with the handling and storage of highly radioactive material. JRC-ITU’s prime objectives are to serve as a reference centre for basic actinide research, to contribute to an effective safety and safeguards system for the nuclear fuel cycle, and to study technological and medical applications of radionuclides/actinides.
Contact: Jean-Paul Glatz Send message
Horia Hulubei, National Institute of Physics and Nuclear Engineering (IFIN-HH)
Contact: Vlad Avrigeanu Send message
Related Research Areas
Key Topic 2: Wasteforms and their Behaviour
This research aims to improve understanding of the behaviour of various wastes in geological disposal facilities in order to better quantify the processes controlling radionuclide, chemical and gas release from waste forms, to improve the quality of models used in safety assessments and to adequately define the types and magnitudes of uncertainties associated with various processes.