EPJ Nuclear Sciences & Technologies最新文献_第5页

Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS MYRRHA对欧盟高放废物管理战略的划分和转变贡献以及MYRRHA相关FP7和H2020项目的主要成就：MYRTE、MARISA、MAXSIMA、SEARCH、MAX、FREYA、ARCAS

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-09-01 DOI: 10.1051/epjn/2019038

H. Abderrahim, P. Baeten, A. Sneyers, M. Schyns, P. Schuurmans, A. Kochetkov, G. Eynde, J. Biarrotte

{"title":"Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS","authors":"H. Abderrahim, P. Baeten, A. Sneyers, M. Schyns, P. Schuurmans, A. Kochetkov, G. Eynde, J. Biarrotte","doi":"10.1051/epjn/2019038","DOIUrl":"https://doi.org/10.1051/epjn/2019038","url":null,"abstract":"Today, nuclear power produces 11% of the world's electricity. Nuclear power plants produce virtually no greenhouse gases or air pollutants during their operation. Emissions over their entire life cycle are very low. Nuclear energy's potential is essential to achieving a deeply decarbonized energy future in many regions of the world as of today and for decades to come, the main value of nuclear energy lies in its potential contribution to decarbonizing the power sector. Nuclear energy's future role, however, is highly uncertain for several reasons: chiefly, escalating costs and, the persistence of historical challenges such as spent fuel and radioactive waste management. Advanced nuclear fuel recycling technologies can enable full use of natural energy resources while minimizing proliferation concerns as well as the volume and longevity of nuclear waste. Partitioning and Transmutation (P&T) has been pointed out in numerous studies as the strategy that can relax constraints on geological disposal, e.g. by reducing the waste radiotoxicity and the footprint of the underground facility. Therefore, a special effort has been made to investigate the potential role of P&T and the related options for waste management all along the fuel cycle. Transmutation based on critical or sub-critical fast spectrum transmuters should be evaluated in order to assess its technical and economic feasibility and capacity, which could ease deep geological disposal implementation.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019038","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47612547","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

Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF2-UF4 salt [U(IV)]/[U(III)]配比对燃料LiF-BeF2-UF4盐中哈氏合金选择性铬腐蚀和碲晶间开裂的影响

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-09-01 DOI: 10.1051/epjn/2019033

A. Surenkov, V. Ignatiev, M. Presnyakov, Jianqiang Wang, Zhijun Li, Xinmei Yang, Z. Dai

引用次数: 8

Innovative Gen-II/III and research reactors' fuels and materials 创新的第II/III代和研究反应堆的燃料和材料

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-06-01 DOI: 10.1051/epjn/2019008

P. Agostini, M. Utili, K. Lambrinou, Heikki Keinänen, P. Karjalainen-Roikonen, Mariana Arnoult Ruzickova

引用次数: 1

Nuclear and radiological emergency management and preparedness 核和放射性应急管理和准备

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-06-01 DOI: 10.1051/epjn/2019011

F. Rocchi, I. Devol-Brown, W. Raskob

引用次数: 1

Advances on GenIV structural and fuel materials and cross-cutting activities between fission and fusion GenIV结构和燃料材料的研究进展以及裂变和聚变之间的交叉活动

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-06-01 DOI: 10.1051/epjn/2019021

L. Malerba, P. Agostini, M. Bertolus, F. Delage, A. Gallais-During, C. Grisolia, K. Liger, P. Giroux

引用次数: 5

Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects 先进的数值模拟和反应堆安全建模-来自CORTEX, HPMC, McSAFE和NURESAFE项目的贡献

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-06-01 DOI: 10.1051/EPJN/2019006

C. Demazière, V. Sánchez-Espinoza, B. Chanaron

{"title":"Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects","authors":"C. Demazière, V. Sánchez-Espinoza, B. Chanaron","doi":"10.1051/EPJN/2019006","DOIUrl":"https://doi.org/10.1051/EPJN/2019006","url":null,"abstract":"Predictive modelling capabilities have long represented one of the pillars of reactor safety. In this paper, an account of some projects funded by the European Commission within the seventh Framework Program (HPMC and NURESAFE projects) and Horizon 2020 Program (CORTEX and McSAFE) is given. Such projects aim at, among others, developing improved solution strategies for the modelling of neutronics, thermal-hydraulics, and/or thermo-mechanics during normal operation, reactor transients and/or situations involving stationary perturbations. Although the different projects have different focus areas, they all capitalize on the most recent advancements in deterministic and probabilistic neutron transport, as well as in DNS, LES, CFD and macroscopic thermal-hydraulics modelling. The goal of the simulation strategies is to model complex multi-physics and multi-scale phenomena specific to nuclear reactors. The use of machine learning combined with such advanced simulation tools is also demonstrated to be capable of providing useful information for the detection of anomalies during operation.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/EPJN/2019006","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49133116","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: 9

Supporting infrastructures and research reactors: status, needs and international cooperation, IAEA ICERR (International CEntres based on Research Reactors) and IGORR (International Group on Research Reactors), FP7 and H2020 JHR access rights 支持基础设施和研究堆:现状、需求和国际合作，原子能机构ICERR(基于研究堆的国际中心)和国际研究堆小组IGORR(国际研究堆小组)，FP7和H2020 JHR访问权

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-06-01 DOI: 10.1051/epjn/2019022

G. Bignan, J. Blanc

{"title":"Supporting infrastructures and research reactors: status, needs and international cooperation, IAEA ICERR (International CEntres based on Research Reactors) and IGORR (International Group on Research Reactors), FP7 and H2020 JHR access rights","authors":"G. Bignan, J. Blanc","doi":"10.1051/epjn/2019022","DOIUrl":"https://doi.org/10.1051/epjn/2019022","url":null,"abstract":"The panorama of research reactors in the world is at a turning point, with many old ones being shutdown, a very few new ones under construction and many newcomer countries interested to get access to one or to build one domestic research reactor or zero-power reactor. In this evolving context, several actions have been set up to answer this international collaboration need: the IAEA has launched the ICERR initiative, the OECD/NEA is proposing the P2M joint project proposal. In France, the Jules Horowitz Reactor (JHR), under construction at CEA Cadarache, within an International Consortium, will be one of the few tools available for the industry and research in the next decades. The paper presents some update of its construction, its experimental capacities and the European support through FP7 and H2020 tools. This paper provides also some insights of international tools (ICERR, P2M) and about the International Group on Research Reactors (IGORR) and how they complement or interact with the JHR.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019022","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43165701","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: 3

Beacon: bentonite mechanical evolution 灯塔:膨润土力学演化

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-05-01 DOI: 10.1051/epjn/2019045

P. Sellin, M. Westermark, O. Leupin, S. Norris, A. Gens, K. Wieczorek, J. Talandier, J. Swahn

{"title":"Beacon: bentonite mechanical evolution","authors":"P. Sellin, M. Westermark, O. Leupin, S. Norris, A. Gens, K. Wieczorek, J. Talandier, J. Swahn","doi":"10.1051/epjn/2019045","DOIUrl":"https://doi.org/10.1051/epjn/2019045","url":null,"abstract":"The aim of Beacon is to develop the understanding of fundamental processes that lead to material homogenisation, as well as to improve capabilities for numerical modelling. In earlier assessments of bentonite EBS, the mechanical interaction between the installed bentonite components has been neglected and an “ideal” final state has generally been assumed. Key features of the project are (1) re-evaluation of the available knowledge to extract the crucial data to compile the qualitative and quantitative data and to enhance the conceptual understanding. (2) Enhanced, robust and practical numerical tools based on a good scientific understanding, which have the expected predictive capabilities regarding the evolution of engineered barriers and seals. (3) A developed database with experimental data needed by the quantitative models. (4) Verified calculation tools based on experimental results in different scales. The Beacon project is required for the pan-European objectives at building confidence amongst regulators and stakeholders regarding the performance of the engineered barriers in a geological repository.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2019045","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46506505","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: 11

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor CROCUS反应堆PETALE实验程序设计研究的不确定性传播

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-04-08 DOI: 10.1051/epjn/2020004

A. Laureau, V. Lamirand, D. Rochman, A. Pautz

引用次数: 2

Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method 用“物理不确定界限”方法验证由实验数据统计分析得到的核数据不确定度

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EPJ Nuclear Sciences & Technologies Pub Date : 2020-02-01 DOI: 10.1051/epjn/2020007

D. Neudecker, M. White, D. Vaughan, G. Srinivasan

{"title":"Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method","authors":"D. Neudecker, M. White, D. Vaughan, G. Srinivasan","doi":"10.1051/epjn/2020007","DOIUrl":"https://doi.org/10.1051/epjn/2020007","url":null,"abstract":"Concerns within the nuclear data community led to substantial increases of Neutron Data Standards (NDS) uncertainties from its previous to the current version. For example, those associated with the NDS reference cross section 239Pu(n,f) increased from 0.6–1.6% to 1.3–1.7% from 0.1–20 MeV. These cross sections, among others, were adopted, e.g., by ENDF/B-VII.1 (previous NDS) and ENDF/B-VIII.0 (current NDS). There has been a strong desire to be able to validate these increases based on objective criteria given their impact on our understanding of various application uncertainties. Here, the “Physical Uncertainty Bounds” method (PUBs) by Vaughan et al. is applied to validate evaluated uncertainties obtained by a statistical analysis of experimental data. We investigate with PUBs whether ENDF/B-VII.1 or ENDF/B-VIII.0 239Pu(n,f) cross-section uncertainties are more realistic given the information content used for the actual evaluation. It is shown that the associated conservative (1.5–1.8%) and minimal realistic (1.1–1.3%) uncertainty bounds obtained by PUBs enclose ENDF/B-VIII.0 uncertainties and indicate that ENDF/B-VII.1 uncertainties are underestimated.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":" ","pages":""},"PeriodicalIF":0.5,"publicationDate":"2020-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1051/epjn/2020007","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47946625","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: 6