W. Ambrosini, R. Lo Frano, L. Cizelj, Pedro Dieguez-Porras, E. Urbonavicius, Iskren Cvetkov, D. Diaconu, J. Kloosterman, R. Konings
The paper highlights the main features of some Euratom projects, which have been running recently in support to education, training and mobility in the nuclear fields. The described projects address various critical aspects of nuclear knowledge management, aiming at maintaining the wealth of nuclear expertise in Europe in an environment characterised by decreased attractiveness of nuclear careers. In an effort to broaden the cooperation and to further extend the opportunities for mobility, some projects ran in parallel with similar initiatives undertaken beyond the European borders. The lesson learnt in terms of successes achieved and critical aspects revealed by the different actions are finally discussed also considering recent recommendations and assessed scenarios by the European Commission for the decarbonisation of the energy sector.
{"title":"Education, training and mobility: towards a common effort to assure a future workforce in Europe and abroad","authors":"W. Ambrosini, R. Lo Frano, L. Cizelj, Pedro Dieguez-Porras, E. Urbonavicius, Iskren Cvetkov, D. Diaconu, J. Kloosterman, R. Konings","doi":"10.1051/epjn/2019018","DOIUrl":"https://doi.org/10.1051/epjn/2019018","url":null,"abstract":"The paper highlights the main features of some Euratom projects, which have been running recently in support to education, training and mobility in the nuclear fields. The described projects address various critical aspects of nuclear knowledge management, aiming at maintaining the wealth of nuclear expertise in Europe in an environment characterised by decreased attractiveness of nuclear careers. In an effort to broaden the cooperation and to further extend the opportunities for mobility, some projects ran in parallel with similar initiatives undertaken beyond the European borders. The lesson learnt in terms of successes achieved and critical aspects revealed by the different actions are finally discussed also considering recent recommendations and assessed scenarios by the European Commission for the decarbonisation of the energy sector.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019018","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825780","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The aim of the present work is to derive empirically a simple expression of the uncertainties on Charpy transition temperatures (TT), which depends only on the test temperatures and the number of tests at each of these temperatures. Calculations of the TT uncertainties of a RPV steel are performed based on an empirical representation of Charpy test results and a Monte Carlo procedure to generate large numbers of data sets for different test matrices. Applying usual procedures to determine the TT to the generated data sets gives access to the distributions of these quantities from which the uncertainties are calculated.An analytical expression for these uncertainties is proposed.
{"title":"Empirical estimation of uncertainties of Charpy impact testing transition temperatures for an RPV steel","authors":"B. Marini","doi":"10.1051/epjn/2020019","DOIUrl":"https://doi.org/10.1051/epjn/2020019","url":null,"abstract":"The aim of the present work is to derive empirically a simple expression of the uncertainties on Charpy transition temperatures (TT), which depends only on the test temperatures and the number of tests at each of these temperatures. Calculations of the TT uncertainties of a RPV steel are performed based on an empirical representation of Charpy test results and a Monte Carlo procedure to generate large numbers of data sets for different test matrices. Applying usual procedures to determine the TT to the generated data sets gives access to the distributions of these quantities from which the uncertainties are calculated.An analytical expression for these uncertainties is proposed.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826636","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Clean energy production is a challenge, which was so far addressed mainly in the electric power sector. More energy is needed in the form of heat for both district heating and industry. Nuclear power is the only technology fulfilling all 3 sustainability dimensions, namely economy, security of supply and environment. In this context, the European Nuclear Cogeneration Industrial Initiative (NC2I) has launched the projects NC2I-R and GEMINI+ aiming to prepare the deployment of High Temperature Gas-cooled Reactors (HTGR) for this purpose.
{"title":"Nuclear cogeneration with high temperature reactors","authors":"G. Wrochna, M. Fütterer, D. Hittner","doi":"10.1051/epjn/2019023","DOIUrl":"https://doi.org/10.1051/epjn/2019023","url":null,"abstract":"Clean energy production is a challenge, which was so far addressed mainly in the electric power sector. More energy is needed in the form of heat for both district heating and industry. Nuclear power is the only technology fulfilling all 3 sustainability dimensions, namely economy, security of supply and environment. In this context, the European Nuclear Cogeneration Industrial Initiative (NC2I) has launched the projects NC2I-R and GEMINI+ aiming to prepare the deployment of High Temperature Gas-cooled Reactors (HTGR) for this purpose.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019023","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826052","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
M. Herranz, R. Idoeta, K. Amgarou, Frédéric Aspe, Csilla Csöme, S. Boden, M. Crozet
Within the INSIDER project, the WP5 (in situ measurements) has been tasked with analysing the existing systems and methodologies for carrying out these types of measurements in constrained environments, aiming to classify and categorise these environments. An additional task is to organise the participation in in situ intercomparison exercises in real situations, defining the most suitable equipment to carry these out. This paper presents the activities of the WP5 and a summary of the main results obtained in these activities after the first two years of work.
{"title":"INSIDER WP5 (in situ measurements): developed activities, main results and conclusions","authors":"M. Herranz, R. Idoeta, K. Amgarou, Frédéric Aspe, Csilla Csöme, S. Boden, M. Crozet","doi":"10.1051/epjn/2019061","DOIUrl":"https://doi.org/10.1051/epjn/2019061","url":null,"abstract":"Within the INSIDER project, the WP5 (in situ measurements) has been tasked with analysing the existing systems and methodologies for carrying out these types of measurements in constrained environments, aiming to classify and categorise these environments. An additional task is to organise the participation in in situ intercomparison exercises in real situations, defining the most suitable equipment to carry these out. This paper presents the activities of the WP5 and a summary of the main results obtained in these activities after the first two years of work.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"11 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019061","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826303","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
M. Allibert, E. Merle, S. Delpech, D. Gérardin, D. Heuer, A. Laureau, S. Moreau
The molten salt reactor designs, where fissile and fertile materials are dissolved in molten salts, under consideration in the framework of the Generation IV International Forum, present some unusual characteristics in terms of design, operation, safety and also proliferation resistance issues. This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor (MSFR), a large power reactor based on the thorium fuel cycle. Preliminary studies of proliferation resistance are presented here, dedicated to the threat of nuclear material diversion in the MSFR, considering both the reactor system itself and the processing units located onsite.
{"title":"Preliminary proliferation study of the molten salt fast reactor","authors":"M. Allibert, E. Merle, S. Delpech, D. Gérardin, D. Heuer, A. Laureau, S. Moreau","doi":"10.1051/epjn/2019062","DOIUrl":"https://doi.org/10.1051/epjn/2019062","url":null,"abstract":"The molten salt reactor designs, where fissile and fertile materials are dissolved in molten salts, under consideration in the framework of the Generation IV International Forum, present some unusual characteristics in terms of design, operation, safety and also proliferation resistance issues. This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor (MSFR), a large power reactor based on the thorium fuel cycle. Preliminary studies of proliferation resistance are presented here, dedicated to the threat of nuclear material diversion in the MSFR, considering both the reactor system itself and the processing units located onsite.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"6 1","pages":"5"},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019062","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826312","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
G. Rodriguez, Philippe Amphoux, D. Plancq, E. Richebois, F. Varaine, Philippe Bigeon
From 2010 to 2019, the French Alternative Energies and Atomic Commission (CEA) associated with industrial partners realized the Basic Design of a prototype Sodium Fast Reactor. This project was called ASTRID (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration). ASTRID design studies were financed through governmental funds until the end of the basic design. These funds covered also the design studies for the core manufacturing workshop, the refurbishment or construction of large test loops. One year before the term of this Basic Design phase (in 2018), industrial partners, CEA and the French State conducted a review of fast neutrons reactors and fuel cycle strategy. The review which is now translated into the Multiannual Energy Program concluded that the perspective of industrial deployment of Fast Reactors is more distant. Yet it has been concluded to keep this option open, requiring to maintain competences, and to progress on technological barriers and further develop know-how. The strategy for complete closure of nuclear fuel cycle is maintained as a long-term sustainability objective (in the second half of the 21st century). Therefore, as a direct consequence of this decision, the ASTRID project stopped at the end of 2019 at its Basic Design phase. Quickly the question raised on the Knowledge Management (KM) and Know-How capitalization of the huge amount of studies and results realized during ten years (around 23 000 technical documents). Moreover the challenge was to realize this KM process in less than one year, before the ASTRID project team definitive split. The paper is presenting an innovative KM methodology which has been created and specifically performed on the ASTRID project. It is based on a series of interviews and video recordings, all transformed into some New KM tools called “MOOK” (MOOK for Management of Organized Online Knowledge). All these MOOKs considered as “data rich contents” are then inter-connected and linked by the ASTRID Product Breakdown Structure to some fundamental documents, for a comprehensive and quick mapping of the project. They finally form an efficient KM tool recorded in a PLM Software (PLM for Product Lifecycle Management). Thus the ASTRID project team has realized a high level and easy-to-use “GPS” (Global Positioning System) tool to keep the ASTRID history, context, knowledge and know-how for years. This KM methodology can be easily adapted to other nuclear projects and needs.
从2010年到2019年，法国替代能源和原子能委员会(CEA)与工业合作伙伴一起实现了钠快堆原型的基本设计。这个项目被称为ASTRID(先进钠技术反应堆工业示范)。ASTRID设计研究由政府基金资助，直至基本设计结束。这些资金还用于核心制造车间的设计研究、大型试验回路的翻新或建造。在基本设计阶段的前一年(2018年)，工业合作伙伴、CEA和法国政府对快中子反应堆和燃料循环战略进行了审查。现在被翻译成《多年度能源计划》(Multiannual Energy Program)的这份评估报告得出的结论是，快速反应堆的工业部署前景更为遥远。然而，结论是保留这一选择，要求保持能力，并在技术壁垒方面取得进展并进一步发展专门知识。完全关闭核燃料循环的战略作为一项长期可持续性目标(在21世纪下半叶)得以维持。因此，作为这一决定的直接后果，ASTRID项目于2019年底在其基本设计阶段停止。很快就提出了关于知识管理(KM)和专有技术资本化的问题，这是十年来实现的大量研究和成果(大约23000份技术文件)。此外，挑战是在ASTRID项目团队最终分裂之前，在不到一年的时间内实现这个KM过程。本文介绍了一种创新的知识管理方法，该方法已被创建并专门用于ASTRID项目。它是基于一系列的访谈和视频记录，所有这些都转化为一些新的知识管理工具，称为“MOOK”(MOOK for Management of Organized Online Knowledge)。所有这些被认为是“数据丰富内容”的mook，然后通过ASTRID产品分解结构相互连接并链接到一些基本文档，以便全面快速地映射项目。它们最终形成一个有效的知识管理工具，记录在PLM软件(PLM for Product Lifecycle Management)中。因此，ASTRID项目团队已经实现了一个高水平和易于使用的“GPS”(全球定位系统)工具，以保持ASTRID的历史，背景，知识和技术多年。这种知识管理方法可以很容易地适用于其他核项目和需求。
{"title":"The knowledge management on the design of a generation IV sodium fast reactor project at CEA. The case and methodology applied on the Astrid project","authors":"G. Rodriguez, Philippe Amphoux, D. Plancq, E. Richebois, F. Varaine, Philippe Bigeon","doi":"10.1051/epjn/2020016","DOIUrl":"https://doi.org/10.1051/epjn/2020016","url":null,"abstract":"From 2010 to 2019, the French Alternative Energies and Atomic Commission (CEA) associated with industrial partners realized the Basic Design of a prototype Sodium Fast Reactor. This project was called ASTRID (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration). ASTRID design studies were financed through governmental funds until the end of the basic design. These funds covered also the design studies for the core manufacturing workshop, the refurbishment or construction of large test loops. One year before the term of this Basic Design phase (in 2018), industrial partners, CEA and the French State conducted a review of fast neutrons reactors and fuel cycle strategy. The review which is now translated into the Multiannual Energy Program concluded that the perspective of industrial deployment of Fast Reactors is more distant. Yet it has been concluded to keep this option open, requiring to maintain competences, and to progress on technological barriers and further develop know-how. The strategy for complete closure of nuclear fuel cycle is maintained as a long-term sustainability objective (in the second half of the 21st century). Therefore, as a direct consequence of this decision, the ASTRID project stopped at the end of 2019 at its Basic Design phase. Quickly the question raised on the Knowledge Management (KM) and Know-How capitalization of the huge amount of studies and results realized during ten years (around 23 000 technical documents). Moreover the challenge was to realize this KM process in less than one year, before the ASTRID project team definitive split. The paper is presenting an innovative KM methodology which has been created and specifically performed on the ASTRID project. It is based on a series of interviews and video recordings, all transformed into some New KM tools called “MOOK” (MOOK for Management of Organized Online Knowledge). All these MOOKs considered as “data rich contents” are then inter-connected and linked by the ASTRID Product Breakdown Structure to some fundamental documents, for a comprehensive and quick mapping of the project. They finally form an efficient KM tool recorded in a PLM Software (PLM for Product Lifecycle Management). Thus the ASTRID project team has realized a high level and easy-to-use “GPS” (Global Positioning System) tool to keep the ASTRID history, context, knowledge and know-how for years. This KM methodology can be easily adapted to other nuclear projects and needs.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826582","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The H2020 Euratom European project INSIDER (Improved Nuclear Site Characterization for waste minimization in decommissioning under constrained environment) was launched in June 2017 for a duration of 4 years; it currently includes 17 partners from 10 European countries. The project is focused onto radiological characterization applied to waste-driven integrated approaches, including the sampling overall strategy and design. Its objectives are to improve the management of waste with medium (MA) and high radioactivity (HA) levels coming from nuclear sites or facilities under D&D (Decommissioning and dismantling) and/or other constrained environments. The optimization criteria refer to operational decommissioning efficiency, safety and costs. The outcome of the project will increase knowledge on the amounts and characteristics of radioactive waste resulting from D&D and increase confidence on the sound definition of subsequent storage and disposal end points. INSIDER is thus mainly focused on the issues of precharacterization upstream of decommissioning operations. The methodology is based on advanced statistical processing and modelling, coupled with validated measurement techniques and methods, in situ or in laboratory, with a final objective of economic gains, and improved safety and sustainability. The technical approach of the project is on one hand to develop different sampling strategies, coupled with characterization methods whose performances are known in representative situations, and on the other hand to qualify the contribution of this approach toand validate its effectiveness in real situations on 3 concrete case studies representing typical configurations of decommissioning worksites: – Nuclear reactor: BR3 reactor vessel at Mol (SCK-CEN); – Installation of the fuel/waste cycle: effluent tanks at ISPRA (JRC); – Post-incident management: contaminated soils (CEA).
{"title":"INSIDER","authors":"D. Roudil, L. Aldave de Las Heras","doi":"10.1051/epjn/2020010","DOIUrl":"https://doi.org/10.1051/epjn/2020010","url":null,"abstract":"The H2020 Euratom European project INSIDER (Improved Nuclear Site Characterization for waste minimization in decommissioning under constrained environment) was launched in June 2017 for a duration of 4 years; it currently includes 17 partners from 10 European countries. The project is focused onto radiological characterization applied to waste-driven integrated approaches, including the sampling overall strategy and design. Its objectives are to improve the management of waste with medium (MA) and high radioactivity (HA) levels coming from nuclear sites or facilities under D&D (Decommissioning and dismantling) and/or other constrained environments. The optimization criteria refer to operational decommissioning efficiency, safety and costs. The outcome of the project will increase knowledge on the amounts and characteristics of radioactive waste resulting from D&D and increase confidence on the sound definition of subsequent storage and disposal end points. INSIDER is thus mainly focused on the issues of precharacterization upstream of decommissioning operations. The methodology is based on advanced statistical processing and modelling, coupled with validated measurement techniques and methods, in situ or in laboratory, with a final objective of economic gains, and improved safety and sustainability. The technical approach of the project is on one hand to develop different sampling strategies, coupled with characterization methods whose performances are known in representative situations, and on the other hand to qualify the contribution of this approach toand validate its effectiveness in real situations on 3 concrete case studies representing typical configurations of decommissioning worksites: – Nuclear reactor: BR3 reactor vessel at Mol (SCK-CEN); – Installation of the fuel/waste cycle: effluent tanks at ISPRA (JRC); – Post-incident management: contaminated soils (CEA).","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2020010","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826885","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The development and safe operation of nuclear installations in Europe is of vital importance for the future of nuclear energy. Helping to ensure the safe operation of nuclear power has always been one of the top priorities of Euratom Research Framework Programmes. With the incentives of Horizon 2020, further integration towards an EU/Euratom Research Area was achieved, better prioritisation at European and International levels based on updates of Research and Innovation agendas or deployment strategies, capitalisation of European Technology platforms and enhanced cooperation with International Organisations or Fora effectively happened. Evolutions towards European Joint Programmes together with EU/Euratom Member States, confirm that research and innovation programmes successfully benefit from a truly added value of a concerted European approach in nuclear safety research and training advocated by the European Commission and EU/Euratom Member States.
{"title":"Euratom Research and Training in 2019: challenges, achievements and future perspectives","authors":"R. Garbil, Christophe Davies, D. Diaconu","doi":"10.1051/epjn/2019035","DOIUrl":"https://doi.org/10.1051/epjn/2019035","url":null,"abstract":"The development and safe operation of nuclear installations in Europe is of vital importance for the future of nuclear energy. Helping to ensure the safe operation of nuclear power has always been one of the top priorities of Euratom Research Framework Programmes. With the incentives of Horizon 2020, further integration towards an EU/Euratom Research Area was achieved, better prioritisation at European and International levels based on updates of Research and Innovation agendas or deployment strategies, capitalisation of European Technology platforms and enhanced cooperation with International Organisations or Fora effectively happened. Evolutions towards European Joint Programmes together with EU/Euratom Member States, confirm that research and innovation programmes successfully benefit from a truly added value of a concerted European approach in nuclear safety research and training advocated by the European Commission and EU/Euratom Member States.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019035","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825961","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
For more than 40 years, considerable scientific and technical knowledge has been acquired in Europe in the field of radioactive waste management, both for near-surface disposal and geological disposal. RD&D will continue to be necessary to develop, maintain and consolidate knowledge throughout the stepwise development, operation and closure of disposal facilities, which will be spread over many decades and make this knowledge available to all end users. Recently, the EC has promoted a step-change in pan-European research cooperation between EU Member States' national programmes by promoting the setting-up of inclusive research joint programmes in Europe gathering those organisations with scientific and technical responsibilities and a national mandate for research in radioactive waste management. Based on the positive achievement of the JOPRAD project (2015–2017), the EC confirmed in 2017 its willingness to co-fund such a Joint Programme in the field of RWM. The RWM community therefore pursued the efforts to establish the Founding Documents (Vision, Strategic Research Agenda, Roadmap, Deployment) and a Work Plan for a first implementation phase of 5-years (2019–2024). In June 2019 the Joint Programme − EURAD − was accepted by the European Commission.
{"title":"EURAD − the European Joint Programme for research on radioactive waste management between EU members states national programmes","authors":"Mariela García, T. Beattie, S. Schumacher","doi":"10.1051/epjn/2019044","DOIUrl":"https://doi.org/10.1051/epjn/2019044","url":null,"abstract":"For more than 40 years, considerable scientific and technical knowledge has been acquired in Europe in the field of radioactive waste management, both for near-surface disposal and geological disposal. RD&D will continue to be necessary to develop, maintain and consolidate knowledge throughout the stepwise development, operation and closure of disposal facilities, which will be spread over many decades and make this knowledge available to all end users. Recently, the EC has promoted a step-change in pan-European research cooperation between EU Member States' national programmes by promoting the setting-up of inclusive research joint programmes in Europe gathering those organisations with scientific and technical responsibilities and a national mandate for research in radioactive waste management. Based on the positive achievement of the JOPRAD project (2015–2017), the EC confirmed in 2017 its willingness to co-fund such a Joint Programme in the field of RWM. The RWM community therefore pursued the efforts to establish the Founding Documents (Vision, Strategic Research Agenda, Roadmap, Deployment) and a Work Plan for a first implementation phase of 5-years (2019–2024). In June 2019 the Joint Programme − EURAD − was accepted by the European Commission.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"1 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019044","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826072","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
E. González, A. Junghans, A. Plompen, P. Schillebeeckx
Nuclear data and associated tools are critical elements of the nuclear energy industry and research, playing an essential role in the simulation of nuclear systems, safety and performance calculations and interpretation of the reactor instrumentation. Nuclear data improvement requires a combination of much different know-hows that are distributed over many small- and medium-sized institutions along Europe. The Euratom programs have facilitated the setup of pan European collaborations getting together the required experience inside the projects CHANDA, ERINDA and the JRC action EUFRAT. The paper describes the holistic and inclusive approach of these projects that have also worked together to coordinate the European nuclear data research capabilities to improve the facilities, detectors, models and evaluation, validation and simulation tools. It also shows examples of success histories and summary of results of these projects and of their impact on the EU nuclear safety and industry, together with an outlook to the future.
{"title":"Nuclear data research supported by EURATOM: CHANDA, ERINDA and EUFRAT","authors":"E. González, A. Junghans, A. Plompen, P. Schillebeeckx","doi":"10.1051/epjn/2019024","DOIUrl":"https://doi.org/10.1051/epjn/2019024","url":null,"abstract":"Nuclear data and associated tools are critical elements of the nuclear energy industry and research, playing an essential role in the simulation of nuclear systems, safety and performance calculations and interpretation of the reactor instrumentation. Nuclear data improvement requires a combination of much different know-hows that are distributed over many small- and medium-sized institutions along Europe. The Euratom programs have facilitated the setup of pan European collaborations getting together the required experience inside the projects CHANDA, ERINDA and the JRC action EUFRAT. The paper describes the holistic and inclusive approach of these projects that have also worked together to coordinate the European nuclear data research capabilities to improve the facilities, detectors, models and evaluation, validation and simulation tools. It also shows examples of success histories and summary of results of these projects and of their impact on the EU nuclear safety and industry, together with an outlook to the future.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":"226 1","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019024","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826101","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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