S. Bourg, A. Geist, J. Adnet, C. Rhodes, B. Hanson
Processes such as PUREX allow the recovery and reuse of the uranium and the plutonium of GEN II/GEN III reactors and are being adapted for the recycling of the uranium and the plutonium of GEN IV MOX fuels. However, it does not fix the sensitive issue of the long-term management of the high active nuclear waste (HAW). Indeed, only the recovery and the transmutation of the minor actinides can reduce this burden down to a few hundreds of years. In this context, and in the continuity of the FP7 EURATOM SACSESS project, GENIORS focuses on the reprocessing of MOX fuel containing minor actinides, taking into account safety issues under normal and mal-operation. By implementing a three-step approach (reinforcement of the scientific knowledge => process development and testing => system studies, safety and integration), GENIORS will provide more science-based strategies for nuclear fuel management in the EU.
{"title":"Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects","authors":"S. Bourg, A. Geist, J. Adnet, C. Rhodes, B. Hanson","doi":"10.1051/epjn/2019009","DOIUrl":"https://doi.org/10.1051/epjn/2019009","url":null,"abstract":"Processes such as PUREX allow the recovery and reuse of the uranium and the plutonium of GEN II/GEN III reactors and are being adapted for the recycling of the uranium and the plutonium of GEN IV MOX fuels. However, it does not fix the sensitive issue of the long-term management of the high active nuclear waste (HAW). Indeed, only the recovery and the transmutation of the minor actinides can reduce this burden down to a few hundreds of years. In this context, and in the continuity of the FP7 EURATOM SACSESS project, GENIORS focuses on the reprocessing of MOX fuel containing minor actinides, taking into account safety issues under normal and mal-operation. By implementing a three-step approach (reinforcement of the scientific knowledge => process development and testing => system studies, safety and integration), GENIORS will provide more science-based strategies for nuclear fuel management in the EU.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019009","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825553","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 European Atomic Energy Community (Euratom) Research and Training framework programmes are benefitting from a consistent success in pursuing excellence in research and facilitating Pan European collaborative efforts across a broad range of nuclear science and technologies, nuclear fission and radiation protection. To fulfil Euratom R&D programmes key objectives of maintaining high levels of nuclear knowledge and building a more dynamic and competitive European industry, promotion of Pan-European mobility of researchers are implemented by co-financing transnational access to research infrastructures and joint research activities through Research and Innovation and Coordination and Support Actions' funding schemes. Establishment by the research community of European technology platforms are being capitalised. Mapping of research infrastructures and E&T capabilities is allowing a closer cooperation within the European Union and beyond, benefiting from multilateral international agreements and from closer cooperation between Euratom, OECD/NEA, IAEA and international fora. ‘Euratom success stories' in facilitating Pan-European E&T collaborative efforts through Research and Training framework programmes show the benefits of research efforts in key fields, of building an effective ‘critical mass’ and implementing European MSc curricula, of promoting the creation of ‘Centre of Excellence’ with an increased support for ‘Open access to key research infrastructures’, exploitation of research results, management of knowledge, dissemination and sharing of learning outcomes.
{"title":"Euratom success stories in facilitating pan-European education and training collaborative efforts","authors":"R. Garbil","doi":"10.1051/epjn/2019016","DOIUrl":"https://doi.org/10.1051/epjn/2019016","url":null,"abstract":"The European Atomic Energy Community (Euratom) Research and Training framework programmes are benefitting from a consistent success in pursuing excellence in research and facilitating Pan European collaborative efforts across a broad range of nuclear science and technologies, nuclear fission and radiation protection. To fulfil Euratom R&D programmes key objectives of maintaining high levels of nuclear knowledge and building a more dynamic and competitive European industry, promotion of Pan-European mobility of researchers are implemented by co-financing transnational access to research infrastructures and joint research activities through Research and Innovation and Coordination and Support Actions' funding schemes. Establishment by the research community of European technology platforms are being capitalised. Mapping of research infrastructures and E&T capabilities is allowing a closer cooperation within the European Union and beyond, benefiting from multilateral international agreements and from closer cooperation between Euratom, OECD/NEA, IAEA and international fora. ‘Euratom success stories' in facilitating Pan-European E&T collaborative efforts through Research and Training framework programmes show the benefits of research efforts in key fields, of building an effective ‘critical mass’ and implementing European MSc curricula, of promoting the creation of ‘Centre of Excellence’ with an increased support for ‘Open access to key research infrastructures’, exploitation of research results, management of knowledge, dissemination and sharing of learning outcomes.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019016","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825718","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 objective of INSIDER work package 3 (WP 3) is to draft a sampling guide for initial nuclear site characterization in constrained environments, based on a statistical approach. In this paper, deliverable 3.4 (D 3.4) is presented for WP 3, where the strategy developed in deliverables 3.1 (D 3.1) to 3.3 (D 3.3) is applied to the first of three reference use cases representative of existing decommissioning scenarios. The present discussion focuses on use case 1 (UC1): the liquid waste storage facility at the JRC site of Ispra (Italy). The proposed characterization strategy developed in D 3.2 is applied in a step by step approach to analyse the pre-existing information (obtained through the use of a pre-sampling questionnaire), and to utilise the available inputs towards the development of a sampling plan sufficient for allowing radiological characterization. The proposed sampling plan follows a three-step approach, i.e. determination of possible elevation in activity concentration by non-destructive testing, biased sampling of layers identified, and finally unbiased sampling after mixing of tank contents.
{"title":"UC1 sampling plan, liquid waste storage tanks, JRC Ispra","authors":"G. V. Oertzen, O. Nitzsche, Artur Hashymov","doi":"10.1051/epjn/2019043","DOIUrl":"https://doi.org/10.1051/epjn/2019043","url":null,"abstract":"The objective of INSIDER work package 3 (WP 3) is to draft a sampling guide for initial nuclear site characterization in constrained environments, based on a statistical approach. In this paper, deliverable 3.4 (D 3.4) is presented for WP 3, where the strategy developed in deliverables 3.1 (D 3.1) to 3.3 (D 3.3) is applied to the first of three reference use cases representative of existing decommissioning scenarios. The present discussion focuses on use case 1 (UC1): the liquid waste storage facility at the JRC site of Ispra (Italy). The proposed characterization strategy developed in D 3.2 is applied in a step by step approach to analyse the pre-existing information (obtained through the use of a pre-sampling questionnaire), and to utilise the available inputs towards the development of a sampling plan sufficient for allowing radiological characterization. The proposed sampling plan follows a three-step approach, i.e. determination of possible elevation in activity concentration by non-destructive testing, biased sampling of layers identified, and finally unbiased sampling after mixing of tank contents.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019043","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826017","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}
We consider a model of neutron-nuclear wave burning. The traveling wave of nuclear burning of the medium is initiated by an external neutron source and is the basis for the new generation reactors the so-called “traveling-wave reactors”. We develop a model of nuclear traveling wave burning, for which it is possible to draw a Newton’s second law analogy with a mechanical dissipative system. On the basis of this analogy, we find that the wave velocity has a continuous spectrum bounded below. Within the framework of the new model, we show the autowave to be possible for certain neutron energies only. Also we find that two burning modes are possible depending on the control parameters: a traveling autowave and a wave driven by an external neutron source.
{"title":"Newton’s second law analogy for the traveling wave of nuclear burning","authors":"V. Urbanevych, I. Sharph, V. Tarasov, V. Rusov","doi":"10.1051/epjn/2020012","DOIUrl":"https://doi.org/10.1051/epjn/2020012","url":null,"abstract":"We consider a model of neutron-nuclear wave burning. The traveling wave of nuclear burning of the medium is initiated by an external neutron source and is the basis for the new generation reactors the so-called “traveling-wave reactors”. We develop a model of nuclear traveling wave burning, for which it is possible to draw a Newton’s second law analogy with a mechanical dissipative system. On the basis of this analogy, we find that the wave velocity has a continuous spectrum bounded below. Within the framework of the new model, we show the autowave to be possible for certain neutron energies only. Also we find that two burning modes are possible depending on the control parameters: a traveling autowave and a wave driven by an external neutron source.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2020012","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826447","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}
A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.
在蒙特卡罗模拟中，采用了一种相关采样技术来估计截面变化对中子输运的影响。这种实现已经与全蒙特卡罗方法相结合，该方法包括用随机截面文件传播核数据的不确定性。TMC-CS (Total Monte Carlo with correlation Sampling)方法提供了相关计算时间的有趣加速。本文详细介绍了该方法，并结合两个应用案例来验证和说明该技术提供的增益:由不锈钢反射器HMI-001基准反射的高浓缩铀/铁金属芯，以及CROCUS零功率轻水反应堆的PETALE实验方案。
{"title":"Uncertainty propagation based on correlated sampling technique for nuclear data applications","authors":"A. Laureau, V. Lamirand, D. Rochman, A. Pautz","doi":"10.1051/epjn/2020003","DOIUrl":"https://doi.org/10.1051/epjn/2020003","url":null,"abstract":"A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2020003","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826745","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}
We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with a scope ranging from the pressure vessel and primary loop to safety-critical software systems and electrical cables. The paper discusses scientific challenges faced in the beginning and achievements made throughout the projects, including the industrial impact and lessons learned. Two particular aspects highlighted concern the way the projects sought contact with end users, and the balance between industrial and academic partners. The paper concludes with an outlook on follow-up issues related to the long term operation of nuclear power plants.
我们对三个正在进行的Horizon 2020项目(ADVISE, NOMAD, TEAM CABLES)和一个已经完成的FP7项目(HARMONICS)进行了交叉审查，这些项目涉及核电厂安全相关组件和系统的可靠性，范围从压力容器和主回路到安全关键软件系统和电缆。本文讨论了开始时面临的科学挑战和整个项目所取得的成就，包括工业影响和吸取的教训。两个特别突出的方面涉及项目寻求与最终用户联系的方式，以及工业和学术合作伙伴之间的平衡。最后，对核电站长期运行的后续问题进行了展望。
{"title":"Reactor performance, system reliability, instrumentation and control","authors":"A. Schumm, M. Rabung, G. Marque, J. Hamalainen","doi":"10.1051/epjn/2019017","DOIUrl":"https://doi.org/10.1051/epjn/2019017","url":null,"abstract":"We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with a scope ranging from the pressure vessel and primary loop to safety-critical software systems and electrical cables. The paper discusses scientific challenges faced in the beginning and achievements made throughout the projects, including the industrial impact and lessons learned. Two particular aspects highlighted concern the way the projects sought contact with end users, and the balance between industrial and academic partners. The paper concludes with an outlook on follow-up issues related to the long term operation of nuclear power plants.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019017","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825763","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. Coeck, T. Jung, M. Birschwilks, C. Walther, B. Bazargan-Sabet, Thomas Perko
In the past 5 years several projects were launched in FP7 and H2020 with the aim to support competence building in nuclear by fostering education and training (E&T) initiatives. ENETRAP III, CONCERT, CINCH II, MEET-CINCH, PETRUS and EAGLE deal with advanced E&T in the fields of radiation protection, nuclear chemistry and geological disposal and the transfer of basic knowledge about ionising radiation, its benefits and risks, to the general public. They were launched with the overall objective of maintaining and extending nuclear know-how and competences in Europe and ensuring sustainable knowledge transfer to current and future generations. This paper describes the aims and achievements of these projects and, based on insights and experiences from these projects, provides some recommendations for future policy support regarding maintaining competences in nuclear industry and research.
在过去五年中，FP7和H2020启动了几个项目，旨在通过促进教育和培训(E&T)倡议来支持核能能力建设。ENETRAP III, CONCERT, CINCH II, MEET-CINCH, PETRUS和EAGLE处理辐射防护，核化学和地质处置领域的先进E&T，以及向公众转移有关电离辐射的基本知识，其益处和风险。它们的总目标是保持和扩大欧洲的核知识和能力，并确保向今世后代可持续地转让知识。本文描述了这些项目的目标和成就，并根据这些项目的见解和经验，为未来维持核工业和研究能力的政策支持提供了一些建议。
{"title":"Improved expertise in radiation protection, nuclear chemistry and geological disposal","authors":"M. Coeck, T. Jung, M. Birschwilks, C. Walther, B. Bazargan-Sabet, Thomas Perko","doi":"10.1051/epjn/2019020","DOIUrl":"https://doi.org/10.1051/epjn/2019020","url":null,"abstract":"In the past 5 years several projects were launched in FP7 and H2020 with the aim to support competence building in nuclear by fostering education and training (E&T) initiatives. ENETRAP III, CONCERT, CINCH II, MEET-CINCH, PETRUS and EAGLE deal with advanced E&T in the fields of radiation protection, nuclear chemistry and geological disposal and the transfer of basic knowledge about ionising radiation, its benefits and risks, to the general public. They were launched with the overall objective of maintaining and extending nuclear know-how and competences in Europe and ensuring sustainable knowledge transfer to current and future generations. This paper describes the aims and achievements of these projects and, based on insights and experiences from these projects, provides some recommendations for future policy support regarding maintaining competences in nuclear industry and research.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019020","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826040","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}
D. Siefman, M. Hursin, H. Sjöstrand, G. Schnabel, D. Rochman, A. Pautz
Nuclear data, especially fission yields, create uncertainties in the predicted concentrations of fission products in spent fuel which can exceed engineering target accuracies. Herein, we present a new framework that extends data assimilation methods to burnup simulations by using post-irradiation examination experiments. The adjusted fission yields lowered the bias and reduced the uncertainty of the simulations. Our approach adjusts the model parameters of the code GEF. We compare the BFMC and MOCABA approaches to data assimilation, focusing especially on the effects of the non-normality of GEF’s fission yields. In the application that we present, the best data assimilation framework decreased the average bias of the simulations from 26% to 14%. The average relative standard deviation decreased from 21% to 14%. The GEF fission yields after data assimilation agreed better with those in JEFF3.3. For Pu-239 thermal fission, the average relative difference from JEFF3.3 was 16% before data assimilation and after it was 12%. For the standard deviations of the fission yields, GEF’s were 100% larger than JEFF3.3’s before data assimilation and after were only 4% larger. The inconsistency of the integral data had an important effect on MOCABA, as shown with the Marginal Likelihood Optimization method. When the method was not applied, MOCABA’s adjusted fission yields worsened the bias of the simulations by 30%. BFMC showed that it inherently accounted for this inconsistency. Applying Marginal Likelihood Optimization with BFMC gave a 2% lower bias compared to not applying it, but the results were more poorly converged.
{"title":"Data assimilation of post-irradiation examination data for fission yields from GEF","authors":"D. Siefman, M. Hursin, H. Sjöstrand, G. Schnabel, D. Rochman, A. Pautz","doi":"10.1051/epjn/2020015","DOIUrl":"https://doi.org/10.1051/epjn/2020015","url":null,"abstract":"Nuclear data, especially fission yields, create uncertainties in the predicted concentrations of fission products in spent fuel which can exceed engineering target accuracies. Herein, we present a new framework that extends data assimilation methods to burnup simulations by using post-irradiation examination experiments. The adjusted fission yields lowered the bias and reduced the uncertainty of the simulations. Our approach adjusts the model parameters of the code GEF. We compare the BFMC and MOCABA approaches to data assimilation, focusing especially on the effects of the non-normality of GEF’s fission yields. In the application that we present, the best data assimilation framework decreased the average bias of the simulations from 26% to 14%. The average relative standard deviation decreased from 21% to 14%. The GEF fission yields after data assimilation agreed better with those in JEFF3.3. For Pu-239 thermal fission, the average relative difference from JEFF3.3 was 16% before data assimilation and after it was 12%. For the standard deviations of the fission yields, GEF’s were 100% larger than JEFF3.3’s before data assimilation and after were only 4% larger. The inconsistency of the integral data had an important effect on MOCABA, as shown with the Marginal Likelihood Optimization method. When the method was not applied, MOCABA’s adjusted fission yields worsened the bias of the simulations by 30%. BFMC showed that it inherently accounted for this inconsistency. Applying Marginal Likelihood Optimization with BFMC gave a 2% lower bias compared to not applying it, but the results were more poorly converged.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826532","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 minimization of the sample quantities required by analytical laboratories, as well as the increase of the fastness of the analytical operations are emerging axes for improved radiochemical analyses related to D&D issues. Two microsystem-based protocols were developed for the selective recovery of 55Fe from radioactive samples by solvent extraction. Both protocols were tested on iron solutions in two different microchips. The yields of Fe extraction were compared with macroscale batch experiments. Better performances with more than 80% of iron extracted were obtained with the second protocol, which is based on a reactive transfer of the iron cation, and more suited to the use of microchannels and very low contact times. This study already demonstrate the high potential of microfluidic technology to improve analytical operations on D&D samples. This method will further be validated with radioactive samples.
{"title":"Analysis of radionuclides in microsystem: application to the selective recovery of 55Fe by solvent extraction","authors":"S. Rassou, C. Mariet, T. Vercouter","doi":"10.1051/epjn/2020002","DOIUrl":"https://doi.org/10.1051/epjn/2020002","url":null,"abstract":"The minimization of the sample quantities required by analytical laboratories, as well as the increase of the fastness of the analytical operations are emerging axes for improved radiochemical analyses related to D&D issues. Two microsystem-based protocols were developed for the selective recovery of 55Fe from radioactive samples by solvent extraction. Both protocols were tested on iron solutions in two different microchips. The yields of Fe extraction were compared with macroscale batch experiments. Better performances with more than 80% of iron extracted were obtained with the second protocol, which is based on a reactive transfer of the iron cation, and more suited to the use of microchannels and very low contact times. This study already demonstrate the high potential of microfluidic technology to improve analytical operations on D&D samples. This method will further be validated with radioactive samples.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2020002","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826736","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 7th EU Framework programme project Advanced Safety Assessment Methodologies: “Extended PSA” (ASAMPSA_E, 2013–2016) was aimed at promoting good practices to extend the scope of existing Probabilistic Safety Assessments (PSAs) and the application of such “extended PSA” in decision-making in the European context. This project led to a collection of guidance reports that describe existing practices and identify their limits. Moreover, it allowed identifying some idea for further research in the framework of collaborative activities. The H2020 project “New Approach to Reactor Safety ImprovementS” (NARSIS, 2017–2021) aims at proposing some improvements to be integrated in existing PSA procedures for NPPs, considering single, cascade and combined external natural hazards (earthquakes, flooding, extreme weather, tsunamis). The project will lead to the release of various tools together with recommendations and guidelines for use in nuclear safety assessment, including a Bayesian-based multi-risk framework able to account for causes and consequences of technical, social/organizational and human aspects and a supporting Severe Accident Management decision-making tool for demonstration purposes, as well.
{"title":"Probabilistic safety assessment for internal and external events/European projects H2020-NARSIS and FP7-ASAMPSA_E","authors":"E. Foerster, E. Raimond, Y. Guigueno","doi":"10.1051/epjn/2019012","DOIUrl":"https://doi.org/10.1051/epjn/2019012","url":null,"abstract":"The 7th EU Framework programme project Advanced Safety Assessment Methodologies: “Extended PSA” (ASAMPSA_E, 2013–2016) was aimed at promoting good practices to extend the scope of existing Probabilistic Safety Assessments (PSAs) and the application of such “extended PSA” in decision-making in the European context. This project led to a collection of guidance reports that describe existing practices and identify their limits. Moreover, it allowed identifying some idea for further research in the framework of collaborative activities. The H2020 project “New Approach to Reactor Safety ImprovementS” (NARSIS, 2017–2021) aims at proposing some improvements to be integrated in existing PSA procedures for NPPs, considering single, cascade and combined external natural hazards (earthquakes, flooding, extreme weather, tsunamis). The project will lead to the release of various tools together with recommendations and guidelines for use in nuclear safety assessment, including a Bayesian-based multi-risk framework able to account for causes and consequences of technical, social/organizational and human aspects and a supporting Severe Accident Management decision-making tool for demonstration purposes, as well.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019012","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57825580","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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