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A promising method for zinc injection into the coolant of water-cooled nuclear reactors 一种有前途的向水冷核反应堆冷却剂中注入锌的方法
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-07-09 DOI: 10.1007/s10512-025-01234-8
S. V. Yevropin, V. A. Yurmanov, S. M. Grigorovich, N. D. Gudkov, K. I. Shutko, Ye. V. Yurmanov
{"title":"A promising method for zinc injection into the coolant of water-cooled nuclear reactors","authors":"S. V. Yevropin,&nbsp;V. A. Yurmanov,&nbsp;S. M. Grigorovich,&nbsp;N. D. Gudkov,&nbsp;K. I. Shutko,&nbsp;Ye. V. Yurmanov","doi":"10.1007/s10512-025-01234-8","DOIUrl":"10.1007/s10512-025-01234-8","url":null,"abstract":"<div><p>The present paper considers a promising method for maintaining the water chemistry regime of water-cooled nuclear reactors with adjustment treatment of the coolant with microadditives of zinc as part of a colloidal solution of high-purity zinc oxide. The aggregate stability of the colloidal solution is achieved by a special method for synthesizing finely dispersed zinc oxide powder from gaseous diethyl zinc, followed by grinding the initial particles and separating the largest particles of zinc oxide to prevent their coagulation or adhesion. The latter is confirmed by zeta potential measurements of the colloidal solution. The method proposed in the article ensures simple and safe zinc injection.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"109 - 114"},"PeriodicalIF":0.3,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934584","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
Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent 用Fersal-MD吸附剂净化含铯的碱性液体高放废物
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-07-09 DOI: 10.1007/s10512-025-01227-7
D. V. Markova, K. A. Feoktistov, S. M. Shaydullin, P. V. Kozlov, Ye. N. Zubrilovskiy, V. V. Milyutin
{"title":"Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent","authors":"D. V. Markova,&nbsp;K. A. Feoktistov,&nbsp;S. M. Shaydullin,&nbsp;P. V. Kozlov,&nbsp;Ye. N. Zubrilovskiy,&nbsp;V. V. Milyutin","doi":"10.1007/s10512-025-01227-7","DOIUrl":"10.1007/s10512-025-01227-7","url":null,"abstract":"<div><p>The paper presents the results of an experimental study on the static sorption extraction of cesium from a real solution of alkaline liquid high-level waste using Fersal-MD inorganic finely dispersed sorbent. Three-stage sorption with repeated use of sorbent was carried out; the solution purification coefficients were determined. An application of the method for industrial use was experimentally assessed. Fersal and Fersal-MD sorbents were compared for use in the technology of extracting cesium from alkaline high-level waste.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"61 - 66"},"PeriodicalIF":0.3,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934589","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
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide 含3.35、5和8 wt %氧化钆的VVER铀-钆燃料球团的热物理性质
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-07-09 DOI: 10.1007/s10512-025-01205-z
A. V. Fedotov, E. N. Mikheev, M. A. Lutkov
{"title":"Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide","authors":"A. V. Fedotov,&nbsp;E. N. Mikheev,&nbsp;M. A. Lutkov","doi":"10.1007/s10512-025-01205-z","DOIUrl":"10.1007/s10512-025-01205-z","url":null,"abstract":"<div><p>This study aims to determine the thermophysical properties of industrial uranium-gadolinium oxide fuel pellets containing 3.35, 5, and 8 wt % Gd<sub>2</sub>O<sub>3</sub> in order to evaluate the performance and safety of VVER-type reactor fuels. The obtained experimental data included thermal expansion, specific heat capacity at constant pressure, and thermal diffusivity. In addition, the temperature dependence of thermal conductivity was calculated up to 1900 K for fuels with varying Gd<sub>2</sub>O<sub>3</sub> content. Figures: 5; Tables: 6; References: 12.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 5-6","pages":"281 - 287"},"PeriodicalIF":0.3,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145163280","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
Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt 在NaCl-2CsCl熔体中分离钚、镅和curium混合物的计算模型
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-07-09 DOI: 10.1007/s10512-025-01228-6
A. G. Osipenko, V. V. Smolenski, A. V. Novoselova
{"title":"Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt","authors":"A. G. Osipenko,&nbsp;V. V. Smolenski,&nbsp;A. V. Novoselova","doi":"10.1007/s10512-025-01228-6","DOIUrl":"10.1007/s10512-025-01228-6","url":null,"abstract":"<div><p>Radioisotope thermoelectric generators for biomedical purposes require high-purity <sup>238</sup>Pu. The present article examines a model for its production in NaCl–2CsCl eutectic melt. For this purpose, physicochemical properties of plutonium, americium, and curium treated with an oxygen-chlorine-argon mixture in NaCl-2CsCl melt were studied at the JSC “SRC RIAR” (Dimitrovgrad, Russian Federation). The developed model provides for determining the modes of plutonium dioxide precipitation without americium and curium, as well as for assessing its possible contamination with actinides.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"67 - 72"},"PeriodicalIF":0.3,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934582","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
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants 核破冰船和小型核电站反应堆中E110合金燃料棒包壳的腐蚀
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-07-09 DOI: 10.1007/s10512-025-01223-x
G. V. Kulakov, Yu. V. Konovalov, A. V. Vatulin, A. A. Kosaurov, S. A. Ershov, E. V. Maynikov, A. V. Kozlov, V. I. Sorokin, A. M. Savchenko
{"title":"Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants","authors":"G. V. Kulakov,&nbsp;Yu. V. Konovalov,&nbsp;A. V. Vatulin,&nbsp;A. A. Kosaurov,&nbsp;S. A. Ershov,&nbsp;E. V. Maynikov,&nbsp;A. V. Kozlov,&nbsp;V. I. Sorokin,&nbsp;A. M. Savchenko","doi":"10.1007/s10512-025-01223-x","DOIUrl":"10.1007/s10512-025-01223-x","url":null,"abstract":"<div><p>E110 zirconium alloy is widely used as a cladding for fuel rods in the core of transport reactors, in particular, nuclear icebreakers. The corrosion of these claddings in the conditions of the icebreaker core tends to convert from uniform to pitting. Operational and post-reactor studies show that the performance of fuel rods with E110 zirconium alloy claddings may be limited due to the development of pitting corrosion. The paper provides assumptions aimed at explaining corrosion mechanisms in the core of nuclear icebreakers.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"35 - 39"},"PeriodicalIF":0.3,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934581","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
Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities 用于核电设施γ辐射长期远程监测的光纤传感器
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-25 DOI: 10.1007/s10512-025-01230-y
V. V. Davydov, D. S. Dmitrieva
{"title":"Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities","authors":"V. V. Davydov,&nbsp;D. S. Dmitrieva","doi":"10.1007/s10512-025-01230-y","DOIUrl":"10.1007/s10512-025-01230-y","url":null,"abstract":"<div><p>The paper substantiates the necessity of developing new models of real-time remote systems for monitoring of the radiation situation in difficult conditions. The expediency of using optical fiber systems for this pupose is noted. A sensor for remote real-time measurement of γ‑radiation absorption dose or its rate is presented. The measurement technique is considered, and the features of the sensor operation are noted. The presented research results confirm the measurement error to be less than 6–8%. The prospects for using the developed fiber-optic sensor for long-term monitoring of the radiation situation are noted.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"78 - 86"},"PeriodicalIF":0.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934583","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
Neural network adjustment of characteristics calculated for a power reactor with a daily load schedule 具有日负荷调度的电力反应堆的神经网络特性调整计算
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-25 DOI: 10.1007/s10512-025-01221-z
A. M. Degtyarev, O. A. Seryanina
{"title":"Neural network adjustment of characteristics calculated for a power reactor with a daily load schedule","authors":"A. M. Degtyarev,&nbsp;O. A. Seryanina","doi":"10.1007/s10512-025-01221-z","DOIUrl":"10.1007/s10512-025-01221-z","url":null,"abstract":"<div><p>The present paper considers the possibility of improving the neural network forecast for a power reactor operating in a daily load schedule. We have prepared two simplified one-dimensional models of a VVER reactor: one as the reactor itself and another as its calculation model including several types of deviations from the reactor model for simulating the calculation error. A simple single-layer neural network is trained by comparing data obtained from the calculation and reactor models. The trained neural network effectively refines the results of the calculated forecast for the reactor model beyond the training time interval.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"21 - 26"},"PeriodicalIF":0.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934580","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
Development and demonstration of basics for plasma reprocessing of spent nuclear fuel 乏核燃料等离子体后处理基础的发展和示范
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-25 DOI: 10.1007/s10512-025-01226-8
N. N. Antonov, M. A Valinurov, A. V. Gavrikov, S. D Kuzmichev, A. D. Melnikov, A. P. Oiler, I. S. Samoylov, V. P. Smirnov, R. A. Timirkhanov, R. A. Usmanov, V. V. Shumova, Yu. S. Mochalov, S. M. Savchits, L. P. Sukhanov
{"title":"Development and demonstration of basics for plasma reprocessing of spent nuclear fuel","authors":"N. N. Antonov,&nbsp;M. A Valinurov,&nbsp;A. V. Gavrikov,&nbsp;S. D Kuzmichev,&nbsp;A. D. Melnikov,&nbsp;A. P. Oiler,&nbsp;I. S. Samoylov,&nbsp;V. P. Smirnov,&nbsp;R. A. Timirkhanov,&nbsp;R. A. Usmanov,&nbsp;V. V. Shumova,&nbsp;Yu. S. Mochalov,&nbsp;S. M. Savchits,&nbsp;L. P. Sukhanov","doi":"10.1007/s10512-025-01226-8","DOIUrl":"10.1007/s10512-025-01226-8","url":null,"abstract":"<div><p>The paper presents the results of the research conducted by the JIHT RAS (Moscow, Russian Federation) on plasma reprocessing of spent fuel. The method is developed within the framework of the “Proryv” project direction as one of the operations in the reprocessing of spent nuclear fuel from industrial energy complexes. Experiments were carried out with substances simulating the elements moving in separating plasma. The physical viability of the selected concept for plasma mass separation is substantiated both theoretically and experimentally. The results will be used in a model of a plasma unit with a capacity of up to 0.2 kg/h for the mass separation of spent nuclear fuel. The model is planned for construction to practice technological processes and engineering solutions on various simulating compositions, including those based on depleted uranium.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"54 - 60"},"PeriodicalIF":0.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934685","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
Strength study of composite materials with boron-containing filler for neutron shielding 含硼填料中子屏蔽复合材料的强度研究
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-25 DOI: 10.1007/s10512-025-01232-w
Yu. O. Chetverikov, E. V. Dergacheva, V. V. Tarnavich, A. V. Krotov, M. M. Murashev, I. V. Smirnov
{"title":"Strength study of composite materials with boron-containing filler for neutron shielding","authors":"Yu. O. Chetverikov,&nbsp;E. V. Dergacheva,&nbsp;V. V. Tarnavich,&nbsp;A. V. Krotov,&nbsp;M. M. Murashev,&nbsp;I. V. Smirnov","doi":"10.1007/s10512-025-01232-w","DOIUrl":"10.1007/s10512-025-01232-w","url":null,"abstract":"<div><p>The present paper investigates the radiation resistance of plastic composite materials with a 24–25 wt% boron-containing filler for printing by the fused deposition method. The polymer matrix is acrylonitrile butadiene styrene and polyethylene terephthalate glycol plastics. The introduction of boron reduces the penetration depth of thermal neutrons by 56–78% from 3 to 0.65 mm. Samples of composite and matrix materials were exposed to a plutonium-beryllium neutron source for 130 days. Mechanical tests showed an increase in strength and ductility by ~20% for irradiated polyethylene terephthalate glycol with amorphous boron. No significant changes in the mechanical properties of irradiated plastic matrix samples, as well as acrylonitrile butadiene styrene plastic with boron nitride, were found.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"95 - 101"},"PeriodicalIF":0.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934587","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
Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation 给定数量的气体离心机级联级稳定同位素分离的有效参数
IF 0.3 4区 工程技术
Atomic Energy Pub Date : 2025-06-25 DOI: 10.1007/s10512-025-01229-5
V. A. Palkin
{"title":"Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation","authors":"V. A. Palkin","doi":"10.1007/s10512-025-01229-5","DOIUrl":"10.1007/s10512-025-01229-5","url":null,"abstract":"<div><p>The paper considers two methods developed for calculating squared-off cascades of gas centrifuges taking into account variable separation factors of gas centrifuges and a given concentration of the target isotope in outlet streams. The first method optimizes feeding streams of stages in individual sections corresponding to the stage type; the second uses a calculation scheme varying the cuts of partial component streams for profiling the stage feeding stream changing along the cascade. A computational experiment was conducted to separate molybdenum hexafluoride in a three-stream cascade of two stage types. An example of <sup>92</sup>Mo concentration demonstrates characteristic features of cascades calculated by the compared methods.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"138 1-2","pages":"73 - 77"},"PeriodicalIF":0.3,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144934686","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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