EPJ Nuclear Sciences & Technologies最新文献_第9页

Review of kinetic modulation experiments in low power nuclear reactors 低功率核反应堆动力学调制实验综述

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020017

Yifeng Jiang, B. Geslot, V. Lamirand, P. Leconte

引用次数: 5

Needs of countries with longer timescale for deep geological repository implementation 实施深层地质储存库时间较长的国家的需要

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019042

Bálint Nős

引用次数: 3

Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation 对严重事故条件下核燃料裂变产物释放研究的贡献:pO2对Cs、Mo和Ba形态的影响

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019058

C. L. Gall, F. Audubert, J. Lechelle, Y. Pontillon, J. Hazemann

{"title":"Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation","authors":"C. L. Gall, F. Audubert, J. Lechelle, Y. Pontillon, J. Hazemann","doi":"10.1051/epjn/2019058","DOIUrl":"https://doi.org/10.1051/epjn/2019058","url":null,"abstract":"The objective of this work is to experimentally investigate the effect of the oxygen potential on the fuel and FP chemical behaviour in conditions representative of a severe accident. More specifically, the speciation of Cs, Mo and Ba is investigated. These three highly reactive FP are among the most abundant elements produced through 235U and 239Pu thermal fission and may have a significant impact on human health and environmental contamination in case of a light water reactor severe accident. This work has set out to contribute to the following three fields: providing experimental data on Pressurized Water Reactor (PWR) MOX fuel behaviour submitted to severe accident conditions and related FP speciation; going further in the understanding of FP speciation mechanisms at different stages of a severe accident; developing a method to study volatile FP behaviour, involving the investigation of SIMFuel samples manufactured at low temperature through SPS. In this paper, a focus is made on the impact of the oxygen potential towards the interaction between irradiated MOX fuels and the cladding, the interaction between Mo and Ba under oxidizing conditions and the assessment of the oxygen potential during sintering.","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/2019058","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826233","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: 10

High to Low pellet cladding gap heat transfer modeling methodology in an uncertainty quantification framework for a PWR Rod Ejection Accident with best estimate coupling 具有最佳估计耦合的压水堆堆棒抛射事故的不确定性量化框架中高到低球团包层间隙传热建模方法

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020018

G.-K. Delipei, J. Garnier, J. L. Pallec, B. Normand

{"title":"High to Low pellet cladding gap heat transfer modeling methodology in an uncertainty quantification framework for a PWR Rod Ejection Accident with best estimate coupling","authors":"G.-K. Delipei, J. Garnier, J. L. Pallec, B. Normand","doi":"10.1051/epjn/2020018","DOIUrl":"https://doi.org/10.1051/epjn/2020018","url":null,"abstract":"High to Low modeling approaches can alleviate the computationally expensive fuel modeling in nuclear reactor’s transient uncertainty quantification. This is especially the case for Rod Ejection Accident (REA) in Pressurized Water Reactors (PWR) were strong multi-physics interactions occur. In this work, we develop and propose a pellet cladding gap heat transfer (Hgap) High to Low modeling methodology for a PWR REA in an uncertainty quantification framework. The methodology involves the calibration of a simplified Hgap model based on high fidelity simulations with the fuel-thermomechanics code ALCYONE1. The calibrated model is then introduced into the CEA developed CORPUS Best Estimate (BE) multi-physics coupling between APOLLO3 R © and FLICA4. This creates an Improved Best Estimate (IBE) coupling that is then used for an uncertainty quantification study. The results indicate that with IBE the distance to boiling crisis uncertainty is decreased from 57% to 42%. This is reflected to the decrease of the sensitivity of Hgap. In the BE coupling Hgap was responsible for 50% of the output variance while in IBE it is close to 0. These results show the potential gain of High to Low approaches for Hgap modeling in REA uncertainty analyses.","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":"57826623","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

COSICAF, a fission chamber simulation tool for academic purposes COSICAF，用于学术目的的裂变室模拟工具

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020011

G. de Izarra

引用次数: 2

Fuel fabrication and reprocessing issues: the ASGARD project 燃料制造和后处理问题:ASGARD项目

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019014

C. Ekberg, T. Retegan, E. Týnová, M. Sarsfield, J. Wallenius

引用次数: 3

Science underpinning the safety case of deep geological repositories − challenges in the past and in the future and how to maintain knowledge and competence during operation 深层地质处置库安全案例的科学基础——过去和未来的挑战，以及如何在操作过程中保持知识和能力

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019037

J. Andersson

引用次数: 3

Infrastructure and international cooperation in research and knowledge transfer: supporting access to key infrastructures and pan-European research − lessons learned 研究和知识转移方面的基础设施和国际合作:支持获得关键基础设施和泛欧研究-经验教训

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019019

C. Fazio, K. Nilsson, D. Manara, A. Plompen, A. Bucalossi, S. Bourg, Rik-Wouter Bosch, J. Bouchter, W. Ambrosini, R. L. Frano, L. Cizelj, P. Dieguez

{"title":"Infrastructure and international cooperation in research and knowledge transfer: supporting access to key infrastructures and pan-European research − lessons learned","authors":"C. Fazio, K. Nilsson, D. Manara, A. Plompen, A. Bucalossi, S. Bourg, Rik-Wouter Bosch, J. Bouchter, W. Ambrosini, R. L. Frano, L. Cizelj, P. Dieguez","doi":"10.1051/epjn/2019019","DOIUrl":"https://doi.org/10.1051/epjn/2019019","url":null,"abstract":"Access to research infrastructures has been supported by the European Commission under different financial schemes. During the 6th EURATOM Framework Programme the instrument introduced by the European Commission were the Integrated Infrastructure Initiatives (I-3). Moreover, funding schemes to support Education and Training for students and professional developments were defined also. The main difference between these two funding schemes is that I-3 are topic-driven projects with access to infrastructure components, while the Education and Training related projects have a mobility component that is applied for the different research topics. The outcome of projects as TALISMAN (I-3), EFNUDAT/NUDAME (I-3), GENTLE (mobility), ENEN-plus (mobility), NUGENIA-plus (mobility within TA of NUGENIA) and ESNII-plus (I-3 similar) will be shortly presented as well as the future European Commission plans in the field of access to research infrastructure.","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/2019019","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826025","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

Editorial : progress in the science and technology of nuclear reactors using molten salts 社论:熔盐核反应堆的科学技术进展

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2019063

J. Kloosterman, E. Merle, J. Ragusa

引用次数: 0

Modeling and control of xenon oscillations in thermal neutron reactors 热中子反应堆中氙振荡的建模与控制

IF 0.5

EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI: 10.1051/epjn/2020009

B. Mercier, Zeng Ziliang, C. Liyi, Shao Nuoya

{"title":"Modeling and control of xenon oscillations in thermal neutron reactors","authors":"B. Mercier, Zeng Ziliang, C. Liyi, Shao Nuoya","doi":"10.1051/epjn/2020009","DOIUrl":"https://doi.org/10.1051/epjn/2020009","url":null,"abstract":"We study axial core oscillations due to xenon poisoning in thermal neutron nuclear reactors with simple 1D models: a linear one-group model, a linear two-group model, and a non-linear model taking the Doppler effect into account. Even though nuclear reactor operators have some 3D computer codes to simulate such phenomena, we think that simple models are useful to identify the sensitive parameters, and study the efficiency of basic control laws. Our results are that, for the one-group model, if we denote the migration area by M 2 and by H the height of the core, the sensitive parameter is H/M. H being fixed, for the 2 groups model, there are still 2 sensitive parameters, the first one being replaced by M12+M22 where M12 denotes the migration area for fast neutrons and M22 the migration area for thermal neutrons. We show that the Doppler effect reduces the instability of xenon oscillations in a significant way. Finally, we show that some proportional/integral/derivative (PID) feedback control law can damp out xenon oscillations in a similar way to the well-known Shimazu control law [Y. Shimazu, Continuous guidance procedure for xenon oscillation control, J. Nucl. Sci. Technol. 32, 1159 (1995)]. The numerical models described in our paper have been applied to PWR.","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/2020009","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57826877","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: 5