EPJ Nuclear Sciences & Technologies最新文献

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Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects 核乏燃料分区与嬗变策略研发:SACSESS与genors项目
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019009
S. Bourg, A. Geist, J. Adnet, C. Rhodes, B. Hanson
{"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":"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/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}
引用次数: 13
Euratom success stories in facilitating pan-European education and training collaborative efforts 欧洲原子能共同体在促进泛欧教育和培训合作努力方面的成功故事
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019016
R. Garbil
{"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":"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/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}
引用次数: 1
UC1 sampling plan, liquid waste storage tanks, JRC Ispra UC1取样计划,废液储罐,JRC Ispra
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019043
G. V. Oertzen, O. Nitzsche, Artur Hashymov
{"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":"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/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}
引用次数: 1
Newton’s second law analogy for the traveling wave of nuclear burning 核子燃烧行波的牛顿第二定律类比
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020012
V. Urbanevych, I. Sharph, V. Tarasov, V. Rusov
{"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":"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/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}
引用次数: 1
Uncertainty propagation based on correlated sampling technique for nuclear data applications 核数据应用中基于相关采样技术的不确定性传播
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020003
A. Laureau, V. Lamirand, D. Rochman, A. Pautz
{"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":"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/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}
引用次数: 2
Reactor performance, system reliability, instrumentation and control 反应堆性能,系统可靠性,仪表和控制
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019017
A. Schumm, M. Rabung, G. Marque, J. Hamalainen
{"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":"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/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}
引用次数: 2
Improved expertise in radiation protection, nuclear chemistry and geological disposal 提高辐射防护、核化学和地质处置等方面的专业知识
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019020
M. Coeck, T. Jung, M. Birschwilks, C. Walther, B. Bazargan-Sabet, Thomas Perko
{"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":"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/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}
引用次数: 1
Data assimilation of post-irradiation examination data for fission yields from GEF GEF裂变产率辐照后检验数据的同化
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020015
D. Siefman, M. Hursin, H. Sjöstrand, G. Schnabel, D. Rochman, A. Pautz
{"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":"6 1","pages":"52"},"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}
引用次数: 8
Analysis of radionuclides in microsystem: application to the selective recovery of 55Fe by solvent extraction 微系统中放射性核素的分析:溶剂萃取法选择性回收55Fe的应用
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020002
S. Rassou, C. Mariet, T. Vercouter
{"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":"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/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}
引用次数: 2
Probabilistic safety assessment for internal and external events/European projects H2020-NARSIS and FP7-ASAMPSA_E 内部和外部事件的概率安全评估/欧洲项目H2020-NARSIS和FP7-ASAMPSA_E
IF 0.5
EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019012
E. Foerster, E. Raimond, Y. Guigueno
{"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":"10 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/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}
引用次数: 1
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