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Squared-off cascade with a given concentration of the target component in external streams 外部流中给定目标成分浓度的方形级联
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-19 DOI: 10.1007/s10512-025-01235-7
V. A. Palkin
{"title":"Squared-off cascade with a given concentration of the target component in external streams","authors":"V. A. Palkin","doi":"10.1007/s10512-025-01235-7","DOIUrl":"10.1007/s10512-025-01235-7","url":null,"abstract":"<div><p>The paper presents a method developed for calculating a squared-off cascade with several types of stages along the feeding stream. The method minimizes the total feeding stream of the cascade. Calculations of germanium tetrafluoride separation in cascades with different numbers of sections have been performed. Using the example of <sup>70</sup>Ge concentration, the optimal three-section cascade is demonstrated as effectively approximating the conical profile of <i>R</i>-cascade streams.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"115 - 119"},"PeriodicalIF":0.3,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934688","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
Deformation features of fuel rods with mixed uranium–plutonium nitride fuel 铀-钚混合氮化燃料燃料棒的变形特征
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-12 DOI: 10.1007/s10512-025-01206-y
L. M. Zabudko, A. F. Grachev, S. I. Porollo, E. E. Marinenko, E. A. Zvir, A. V. Belyaeva, F. N. Kryukov, M. V. Skupov
{"title":"Deformation features of fuel rods with mixed uranium–plutonium nitride fuel","authors":"L. M. Zabudko,&nbsp;A. F. Grachev,&nbsp;S. I. Porollo,&nbsp;E. E. Marinenko,&nbsp;E. A. Zvir,&nbsp;A. V. Belyaeva,&nbsp;F. N. Kryukov,&nbsp;M. V. Skupov","doi":"10.1007/s10512-025-01206-y","DOIUrl":"10.1007/s10512-025-01206-y","url":null,"abstract":"<div><p>Fuel rods containing a mixed uranium–plutonium nitride (MNUP) fuel were subjected to irradiation in BOR-60 and BN-600 reactors to assess their performance and potential use in BREST-OD-300 and BN-1200M reactors. Post-irradiation examinations revealed that their deformation behavior differs from that of fuel rods with oxide fuel. Nitride fuel rods demonstrated increased axial elongation and cladding ovalization under identical irradiation conditions within the same assembly. Elongation and ovalization studies were carried out for 12 fuel rods with cold-worked ChS68-ID cladding, 38 rods with cold-worked EK164-ID cladding, and 69 rods with EP823-Sh cladding. The fuel rods were irradiated in 17 experimental fuel assemblies, covering a range of maximum fuel burnup from 3.1–9.1% heavy atoms and displacement damage from 26–108 displacements per atom (dpa). The experimental data suggest that axial elongation is predominantly attributable to axial forces that emerge from thermomechanical interactions between the fuel and cladding. These interactions are attributed to the random displacement of pellets and/or their fragments from an axisymmetric position.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"288 - 294"},"PeriodicalIF":0.3,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145165567","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
Pilot testing of chemical absorbers for protection units of vacuum pumps in collectors of a condensation-evaporation unit at a separation plant 分离装置冷凝蒸发装置集热器中真空泵保护装置用化学吸收剂的中试试验
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01208-w
O. B. Gromov, M. Y. Kornienko, D. V. Utrobin, S. O. Travin
{"title":"Pilot testing of chemical absorbers for protection units of vacuum pumps in collectors of a condensation-evaporation unit at a separation plant","authors":"O. B. Gromov,&nbsp;M. Y. Kornienko,&nbsp;D. V. Utrobin,&nbsp;S. O. Travin","doi":"10.1007/s10512-025-01208-w","DOIUrl":"10.1007/s10512-025-01208-w","url":null,"abstract":"<div><p>This study investigates evacuation schemes for the collector of a condensation-evaporation unit used in a separation plant for treating fluorine-containing gases at pressures of up to 1.3 kPa. The results demonstrate that the efficiency of chemical absorbers depends on process conditions. The scheme employing alkaline absorbers exhibits over fivefold greater efficiency compared to the standard system using activated aluminum oxide. The operability of the pump is shown to correlate with the fluoride ion content in the vacuum oil. When alkaline absorbers are used, the accumulation rate of fluoride ions in the oil is 0.61 g/day, which is nearly 50 times lower than with activated aluminum oxide. Furthermore, the modified mercerized wood used as a chemical absorber exhibits a technological advantage over conventional lime-based absorbers. Figures: 3; Tables: 5; References: 7.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"301 - 309"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164310","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
Sub-channel analysis of fuel assemblies for innovative reactor design using the MATADOR software 使用MATADOR软件对创新反应堆设计的燃料组件进行子通道分析
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01203-1
A. S. Zalesov, A. N. Churkin, A. M. Baisov
{"title":"Sub-channel analysis of fuel assemblies for innovative reactor design using the MATADOR software","authors":"A. S. Zalesov,&nbsp;A. N. Churkin,&nbsp;A. M. Baisov","doi":"10.1007/s10512-025-01203-1","DOIUrl":"10.1007/s10512-025-01203-1","url":null,"abstract":"<div><p>The MATADOR software designed for subchannel thermohydraulic calculations of fuel assemblies with different coolants is being developed at OKB Gidropress JSC. Validation of the program with experimental data on key thermohydraulic parameters in the reactor core is of paramount importance, as it confirms the reliability of the modeling of physical processes and phenomena. The article presents the results of the validation and verification of the MATADOR subchannel program based on a series of experiments with supercritical water cooling of rod bundles conducted in China and at the NACIE-UP test facility in Italy, which has a 19-rod assembly cooled with lead-bismuth coolant. The modeling of rod bundles with wire wrapped spacers was performed using a geometric model. Analysis of the computational studies confirmed the ability of the software to reproduce measurements with acceptable accuracy for engineering practice.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"263 - 270"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164302","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
Prospects of using neutron beams for gamma-resonance spectroscopy 中子束在伽玛共振光谱中的应用前景
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01212-0
V. T. Lebedev, V. S. Kozlov, M. V. Remizov, Yu. V. Kulvelis
{"title":"Prospects of using neutron beams for gamma-resonance spectroscopy","authors":"V. T. Lebedev,&nbsp;V. S. Kozlov,&nbsp;M. V. Remizov,&nbsp;Yu. V. Kulvelis","doi":"10.1007/s10512-025-01212-0","DOIUrl":"10.1007/s10512-025-01212-0","url":null,"abstract":"<div><p>A model of an electrodynamic Mössbauer spectrometer has been developed by the NRC “Kurchatov Institute”—PNPI (Gatchina, Russian Federation). The model represents a prototype using the neutron beam of the PIK reactor, which is generated using either constant or periodic activation of a γ-source, and isotope sources for structural and physicochemical studies of steel and alloys, minerals, catalysts, nanostructures, and biological objects. The article presents the physical characteristics of the model, as well as the sample preparation methodology and measurement modes with sample cooling to liquid nitrogen temperature. The experiments performed on a crystal hydrate with initially divalent iron admixed with Fe<sup>3+</sup> have demonstrated the capabilities of the spectrometer for non-destructive testing of chemical reactions. The potential of the spectrometer in nanotechnology is illustrated by the results of studying magnetic graphene oxide composites and nanodiamonds grafted with europium ions.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"327 - 332"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164303","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
Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes 螺旋管与直管一次通蒸汽通道热工力学对比分析
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01217-9
V. A. Grabezhnaya, A. S. Mikheyev, V. V. Ulyanov
{"title":"Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes","authors":"V. A. Grabezhnaya,&nbsp;A. S. Mikheyev,&nbsp;V. V. Ulyanov","doi":"10.1007/s10512-025-01217-9","DOIUrl":"10.1007/s10512-025-01217-9","url":null,"abstract":"<div><p>This study presents a comparative analysis of the performance of helical and straight-tube steam-generating channels heated by liquid metals. In the straight-tube model, an unsteady heat transfer crisis was observed. Under specific operating conditions, dead zones were documented in both the economizer and superheater sections. The unsteady heat transfer crisis can be eliminated by installing throttling devices at the tube inlet, while the dead zones can only be eliminated by intensifying heat transfer. One approach to enhancing heat transfer is the use of helical tubes. In the helical steam-generating channel, no thermohydraulic instability was detected during longitudinal flow of the coolant along the heat exchange tubes. The findings indicate that helical steam-generating tubes exhibit a substantially higher efficiency when operated with transverse flow than with longitudinal flow.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"366 - 374"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164308","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
Fast reactors with lead-bismuth and lead coolants 使用铅铋和铅冷却剂的快堆
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01202-2
V. M. Troyanov, A. V. Gulevich, G. I. Toshinsky, V. V. Petrochenko, O. G. Komlev, A. V. Kondaurov
{"title":"Fast reactors with lead-bismuth and lead coolants","authors":"V. M. Troyanov,&nbsp;A. V. Gulevich,&nbsp;G. I. Toshinsky,&nbsp;V. V. Petrochenko,&nbsp;O. G. Komlev,&nbsp;A. V. Kondaurov","doi":"10.1007/s10512-025-01202-2","DOIUrl":"10.1007/s10512-025-01202-2","url":null,"abstract":"<div><p>One effective way to restore public confidence in nuclear power following severe accidents is to develop reactors that possess a high degree of inherent self-protection and passive safety features. Examples of such reactors include fast reactors cooled by heavy liquid metals, such as lead-bismuth and lead. These reactors lack the potential energy of compression and the chemical energy accumulated in the coolant which, under certain highly unlikely combinations of initiating events, could cause a release of radionuclides requiring the evacuation of the population. Due to the lack of many safety systems, nuclear power plants with heavy liquid metal coolants may be more competitive by their very nature. Lead-bismuth and lead-based coolants, like all others, have their own advantages and disadvantages. This article presents a comparative analysis of the characteristics of these coolants, their impact on the safety, reliability, and operational characteristics of reactors. It concludes that nuclear reactors with these coolants could find wide application in nuclear power after gaining operational experience with the first prototypes.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"257 - 262"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164309","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
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel 从VVER乏燃料中嬗变Np、Am和Cm的熔盐反应堆的工程和物理设计
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01207-x
A. V. Lopatkin, I . T. Tret’yakov, I. A. Larionov, M. A. Tuktarov, I. V. Zayko, D. S. Klimenko
{"title":"Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel","authors":"A. V. Lopatkin,&nbsp;I . T. Tret’yakov,&nbsp;I. A. Larionov,&nbsp;M. A. Tuktarov,&nbsp;I. V. Zayko,&nbsp;D. S. Klimenko","doi":"10.1007/s10512-025-01207-x","DOIUrl":"10.1007/s10512-025-01207-x","url":null,"abstract":"<div><p>This article presents the engineering and physical design of a molten salt reactor (MSR) with circulating fuel based on LiF–BeF<sub>2</sub> salt mixtures, intended for the transmutation of neptunium (Np), americium (Am), and curium (Cm). Neutronic calculations demonstrate the feasibility of constructing a high-power MSR with a transmutation rate of at least 250 kg/year of Np, Am, and Cm. The proposed reactor layout suggests that a modular loop configuration is optimal for enhancing transmutation efficiency. In this design, the reactor, equipment, and primary circuit pipelines are arranged within a compact protective housing, which serves to minimize the volume of fuel salt outside the reactor core. Figure: 6, Tables: 4, References: 3.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"295 - 300"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164304","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
Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification 核电站安全壳加固束受力监测及应急负荷论证
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01214-y
V. N. Medvedev, A. S. Kiselev, A. S. Kiselev, V. F. Strizhov, A. N. Ulyanov, M. I. Skorikova
{"title":"Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification","authors":"V. N. Medvedev,&nbsp;A. S. Kiselev,&nbsp;A. S. Kiselev,&nbsp;V. F. Strizhov,&nbsp;A. N. Ulyanov,&nbsp;M. I. Skorikova","doi":"10.1007/s10512-025-01214-y","DOIUrl":"10.1007/s10512-025-01214-y","url":null,"abstract":"<div><p>The article describes a methodology justifying the serviceability of a nuclear power plant containment for predicting the forces in the anchors of reinforcement bundles and concluding about their performance without using hydraulic jacks and the lift-off method. The calculation methodology is based on the results of monitoring the forces in each reinforcement bundle using PSI-01 force sensors, as well as on readings from control and measuring equipment, including containment movement sensors.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"342 - 349"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164305","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
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200 在SSC RF-IPPE测试钠加热蒸汽发生器模型：从BN-350到BN-1200
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-11 DOI: 10.1007/s10512-025-01216-w
V. A. Grabezhnaya, A. S. Mikheyev, Yu. A. Kuzina, A. D. Bukreeva
{"title":"Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200","authors":"V. A. Grabezhnaya,&nbsp;A. S. Mikheyev,&nbsp;Yu. A. Kuzina,&nbsp;A. D. Bukreeva","doi":"10.1007/s10512-025-01216-w","DOIUrl":"10.1007/s10512-025-01216-w","url":null,"abstract":"<div><p>This paper presents key test results of various steam generator models evaluated at SSC RF–IPPE JSC to validate designs for sodium-cooled power units. The tests provided critical operational recommendations, including: the required steam superheat temperature to prevent moisture carryover in BN-600 evaporators, the optimum working pressure for BN-350 evaporators to avoid flow instability, and thermodynamic non-equilibrium data for post dryout heat transfer in sodium-heated steam tubes. The study also established stability limits for Field channels and identified unique heat transfer characteristics in high-steam superheated tubes.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"357 - 365"},"PeriodicalIF":0.3,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145164306","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
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