发布求助
文献互助 智能选刊 最新文献

Atomic Energy最新文献

筛选
英文 中文
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods 设计热核反应堆燃料棒线性热率斜坡限制曲线的方法
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-30 DOI: 10.1007/s10512-024-01129-0
A. V. Krupkin, V. I. Kuznetsov, K. V. Loktaev, V. V. Novikov
{"title":"A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods","authors":"A. V. Krupkin,&nbsp;V. I. Kuznetsov,&nbsp;K. V. Loktaev,&nbsp;V. V. Novikov","doi":"10.1007/s10512-024-01129-0","DOIUrl":"10.1007/s10512-024-01129-0","url":null,"abstract":"<div><p>An increase in power during transient operating modes of reactors can lead to the depressurization of fuel rods due to the stress corrosion cracking mechanism. Expansion of fuel pellets due to increasing power induces tensile stresses in the cladding, which can initiate the formation and growth of corrosion cracks in the presence of aggressive fission products. Therefore, the plotted limit curve is primarily aimed at preventing circumferential stresses in the cladding from exceeding a certain maximum value during abrupt changes in power. The present article describes a system for performing multivariate statistical calculations of a single power increase to plot an envelope curve for the permissible area of fuel rod operation. The system uses the START-3A code to perform fuel rod calculations, which includes the ability to vary model and design parameters. The methodology for the calculated limit curve for a rapid increase in the power of a VVER-1200 reactor is presented with examples.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"50 - 56"},"PeriodicalIF":0.4,"publicationDate":"2024-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142452920","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
On the 60th anniversary of the first aperiodic pulsed nuclear reactor in Russia 俄罗斯第一座非周期性脉冲核反应堆 60 周年纪念
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-25 DOI: 10.1007/s10512-024-01123-6
S. A. Andreev, A. V. Lukin, Yu. A. Sokolov, A. A. Kuzinskaya
{"title":"On the 60th anniversary of the first aperiodic pulsed nuclear reactor in Russia","authors":"S. A. Andreev,&nbsp;A. V. Lukin,&nbsp;Yu. A. Sokolov,&nbsp;A. A. Kuzinskaya","doi":"10.1007/s10512-024-01123-6","DOIUrl":"10.1007/s10512-024-01123-6","url":null,"abstract":"<div><p>The article describes the history of creating the first Russian nuclear reactor capable of generating powerful controlled fission pulses. The FKBN‑I reactor was launched in 1964 at NII-1011 (currently FSUE “RFNC—VNIITF named after Academ. E.I. Zababakhin”). Forming the basis of FKBN‑I, pioneering work was carried out on the experimental development of technical solutions and control modes, which were used for the design of aperiodic pulsed reactors. The main neutron-physical characteristics and parameters of first fission pulses are given along with a description of methods for obtaining them. The article also mentions the main developers and researchers involved in the creation of the reactor.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"13 - 19"},"PeriodicalIF":0.4,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142453006","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Feasibility study for industrial conditioning of spent ion-exchange resins by impregnation with a polymer binder 通过浸渍聚合物粘合剂对废离子交换树脂进行工业调节的可行性研究
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-25 DOI: 10.1007/s10512-024-01134-3
E. E. Ostashkina, A. E. Savkin, Yu. T. Slastennikov
{"title":"Feasibility study for industrial conditioning of spent ion-exchange resins by impregnation with a polymer binder","authors":"E. E. Ostashkina,&nbsp;A. E. Savkin,&nbsp;Yu. T. Slastennikov","doi":"10.1007/s10512-024-01134-3","DOIUrl":"10.1007/s10512-024-01134-3","url":null,"abstract":"<div><p>A comparative study of technologies for conditioning reprocessed spent ion-exchange resins was carried out by FSUE “RADON” on laboratory and pilot-industrial scales. According to industrial application criteria, a choice was made in favor of dehydration and impregnation using a polymer binder based on epoxy resins. To implement this technology, a pilot unit was developed and manufactured. Tests of the unit carried out with actual resins demonstrated its operability and the compliance of the resulting polymer compound with regulatory requirements.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"78 - 83"},"PeriodicalIF":0.4,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142453007","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Technical and economic aspects of a nuclear power engineering plant for hydrogen production 制氢核电站的技术和经济问题
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-24 DOI: 10.1007/s10512-024-01122-7
S. A. Fateev, V. V. Petrunin, N. V. Sheshina, I. V. Marov
{"title":"Technical and economic aspects of a nuclear power engineering plant for hydrogen production","authors":"S. A. Fateev,&nbsp;V. V. Petrunin,&nbsp;N. V. Sheshina,&nbsp;I. V. Marov","doi":"10.1007/s10512-024-01122-7","DOIUrl":"10.1007/s10512-024-01122-7","url":null,"abstract":"<div><p>The implementation of an investment project for the construction of a nuclear power engineering plant with high-temperature gas-cooled reactors and chemical engineering facilities for the production of hydrogen-containing products according to hydrocarbon reforming method represents a major development task in the field of hydrogen technologies. The product line of a nuclear power engineering plant consists of hydrogen, ammonia, and carbamide. The final product will be determined by the consumer. For effective technical and design solutions, enterprises cooperate to conduct research and development work on fuel, graphite, high-temperature materials, manufacture elements and components of the main reactor plant equipment, and verify calculation codes, at the same time as developing a regulatory framework and concept for the management of spent nuclear fuel and radioactive waste. As well as reviewing the main technical solutions for the project of a four-unit nuclear power engineering plant with high-temperature gas-cooled reactors and chemical engineering facilities for large-scale hydrogen production, the present article provides an estimate of the hydrogen cost price at various prices for natural gas, taking into account the stages of production, liquefaction, transportation, and storage.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"1 - 12"},"PeriodicalIF":0.4,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142452963","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code 利用 MAVR-TA 代码模拟喷雾系统液滴清除核电厂安全壳大气中的放射性气溶胶
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-18 DOI: 10.1007/s10512-024-01125-4
S. S. Savekin, Yu. B. Shmelkov
{"title":"Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code","authors":"S. S. Savekin,&nbsp;Yu. B. Shmelkov","doi":"10.1007/s10512-024-01125-4","DOIUrl":"10.1007/s10512-024-01125-4","url":null,"abstract":"<div><p>The article presents the results of a simulation of the TOSQAN (France) and CSE (USA) experiments on the capture of aerosol fission product simulators by droplets of the spray system using the MAVR-TA code. The calculation results are well-correlated with experimental data. The main mechanisms for capturing aerosol particles by sprayed droplets under conditions of beyond-design-basis accidents are described. Analytical calculations were carried out to study the effect of aerosol particle density on the efficiency of particle removal. According to the performed calculations, the density of aerosol particles has a significant impact on their removal from the atmosphere of the containment.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"27 - 31"},"PeriodicalIF":0.4,"publicationDate":"2024-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142268852","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors 基于铅冷反应堆的发电厂蒸汽动力循环面临的新挑战
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01126-3
E. P. Kondurov, E. N. Kulakov, A. V. Popov, D. V. Stepanov, A. V. Proukhin, I. D. Shchepetil’nikov, V. V. Khodakovskij
{"title":"New challenges for the steam-power cycle in power plants based on lead-cooled reactors","authors":"E. P. Kondurov,&nbsp;E. N. Kulakov,&nbsp;A. V. Popov,&nbsp;D. V. Stepanov,&nbsp;A. V. Proukhin,&nbsp;I. D. Shchepetil’nikov,&nbsp;V. V. Khodakovskij","doi":"10.1007/s10512-024-01126-3","DOIUrl":"10.1007/s10512-024-01126-3","url":null,"abstract":"<div><p>The current development of lead-cooled reactor plants places the main focus of R&amp;D on the primary circuit of the power plant. However, the high melting point of lead significantly affects the design of the secondary circuit, in particular, necessitating the creation of a special system for heating feedwater at the inlet to steam generators to a temperature that exceeds the melting point of the reactor coolant. The present article substantiates the need for the functional allocation of this system and formulates its main requirements.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"32 - 38"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253523","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
TERMIT technology for developing simulation systems of small nuclear power facilities 用于开发小型核电设施模拟系统的 TERMIT 技术
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01127-2
D. V. Lialiuev, A. A. Shaleninov
{"title":"TERMIT technology for developing simulation systems of small nuclear power facilities","authors":"D. V. Lialiuev,&nbsp;A. A. Shaleninov","doi":"10.1007/s10512-024-01127-2","DOIUrl":"10.1007/s10512-024-01127-2","url":null,"abstract":"<div><p>The paper considers the development and application of digital twins for nuclear power facilities with the purpose of improving operational safety and cost efficiency. The TERMIT technology for automated simulation is presented to develop comprehensive calculation models of various classes and purposes for full-scale simulation of dynamic processes occurring in nuclear power facilities. The main directions and results of the technology application are provided.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"39 - 43"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253525","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Advanced methods for laser dismantling of spent fuel assemblies and fuel rods in the primary operations of the robotic production in a closed nuclear fuel cycle 在封闭式核燃料循环机器人生产的初级操作中激光拆除乏燃料组件和燃料棒的先进方法
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01131-6
A. A. Zherebtsov, Yu. S. Mochalov, A. E. Usmanov, A. N. Rybakov, S. A. Dmitriev, S. A. Shimansky, V. I. Dunaev
{"title":"Advanced methods for laser dismantling of spent fuel assemblies and fuel rods in the primary operations of the robotic production in a closed nuclear fuel cycle","authors":"A. A. Zherebtsov,&nbsp;Yu. S. Mochalov,&nbsp;A. E. Usmanov,&nbsp;A. N. Rybakov,&nbsp;S. A. Dmitriev,&nbsp;S. A. Shimansky,&nbsp;V. I. Dunaev","doi":"10.1007/s10512-024-01131-6","DOIUrl":"10.1007/s10512-024-01131-6","url":null,"abstract":"<div><p>The article describes the basic technical solutions and the composition of units for laser dismantling of spent fuel assemblies and cutting of fuel rods for reactors with a liquid-metal coolant during the processing of spent nuclear fuel. The use of lasers as part of robotic and automated complexes for fuel assembly dismantling and fuel rod fragmentation will reduce the loss of valuable fuel materials, prevent their entrainment, reduce the cost of processing, minimize the contamination of solid radioactive waste with fission products, and optimize primary operations in general.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"62 - 67"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253524","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Sorption of Cs, Np, and Pu by the rocks of the Yeniseisky site depending on the temperature and ionic strength of Mg-K-phosphate leaching solutions 叶尼塞斯基矿址岩石对铯、镎和钚的吸附取决于 Mg-K- 磷酸盐沥滤溶液的温度和离子强度
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01133-4
A. A. Rodionova, S. A. Fimina, S. S. Vorobey, S. E. Vinokurov
{"title":"Sorption of Cs, Np, and Pu by the rocks of the Yeniseisky site depending on the temperature and ionic strength of Mg-K-phosphate leaching solutions","authors":"A. A. Rodionova,&nbsp;S. A. Fimina,&nbsp;S. S. Vorobey,&nbsp;S. E. Vinokurov","doi":"10.1007/s10512-024-01133-4","DOIUrl":"10.1007/s10512-024-01133-4","url":null,"abstract":"<div><p>The study of radionuclide migration is of particular concern in when substantiating safety procedures involved in the deep disposal of radioactive waste in the host rocks of the Yeniseisky site located in Krasnoyarsk Krai. One of the main processes controlling the migration of radionuclides is the sorption by mineral phases of host rocks. The present work aims to obtain quantitative characteristics of <sup>137</sup>Cs, <sup>237</sup>Np, and <sup>239</sup>Pu sorption by the rocks of the Yeniseisky site under conditions simulating a deep disposal of radioactive waste. The distribution coefficients of <sup>137</sup>Cs, <sup>237</sup>Np, and <sup>239</sup>Pu were determined depending on the ionic strength and temperature of the solutions after leaching the Mg-K-phosphate compound. Differences in the effect of K<sup>+</sup> and Mg<sup>2+</sup> cations on cesium sorption by the rocks were established. At an increase in the temperature, the efficiency of <sup>239</sup>Pu and <sup>237</sup>Np sorption by the rocks increases, while the sorption of <sup>137</sup>Cs remains almost constant.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"72 - 77"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253626","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Surface distribution of tritium in the first wall of a fusion reactor according to the data of neutron measurements 根据中子测量数据得出的聚变反应堆第一壁氚的表面分布情况
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01136-1
E. D. Vovchenko, K. I. Kozlovskij, A. E. Shikanov, A. A. Isaev
{"title":"Surface distribution of tritium in the first wall of a fusion reactor according to the data of neutron measurements","authors":"E. D. Vovchenko,&nbsp;K. I. Kozlovskij,&nbsp;A. E. Shikanov,&nbsp;A. A. Isaev","doi":"10.1007/s10512-024-01136-1","DOIUrl":"10.1007/s10512-024-01136-1","url":null,"abstract":"<div><p>The article considers an in-situ method potential for establishing the surface distribution of tritium in the first wall of a fusion reactor using neutron tomography. The method includes the formation of a pulse-periodic flux of accelerated deuterons bombarding the studied surface of the first reactor wall following its saturation with tritium, generation of a fast neutron field according to T (<i>d, n</i>)<sup>4</sup>He reaction, measurement of neutron fluence at given spatial points, and reconstruction of the spatial tritium distribution according to measurement data. An algorithm for such a reconstruction is presented based on an approximate solution to the inverse Fredholm problem.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"91 - 95"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253529","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
首页 上一页 下一页 尾页
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整，为了账户安全，请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们：info@booksci.cn Book学术提供免费学术资源搜索服务，方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号：481959085
Book学术官方微信