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Experimental study of the hydrodynamic characteristics of the coolant flow at the outlet of the fuel assembly for the RITM nuclear icebreaker reactor RITM 破冰船核反应堆燃料组件出口冷却剂流体力学特性实验研究
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01130-7
S. M. Dmitriev, T. D. Demkina, A. A. Dobrov, D. V. Doronkov, D. S. Doronkova, D. D. Kuritsin, A. N. Pronin, A. V. Ryazanov
{"title":"Experimental study of the hydrodynamic characteristics of the coolant flow at the outlet of the fuel assembly for the RITM nuclear icebreaker reactor","authors":"S. M. Dmitriev,&nbsp;T. D. Demkina,&nbsp;A. A. Dobrov,&nbsp;D. V. Doronkov,&nbsp;D. S. Doronkova,&nbsp;D. D. Kuritsin,&nbsp;A. N. Pronin,&nbsp;A. V. Ryazanov","doi":"10.1007/s10512-024-01130-7","DOIUrl":"10.1007/s10512-024-01130-7","url":null,"abstract":"<div><p>The paper presents experimentally determined hydrodynamic characteristics of the coolant flow at the outlet of the RITM nuclear icebreaker reactor fuel assembly. The studies were carried out according to Pitot tube measurements based on the theory of hydrodynamic similarity using a model of the fuel assembly outlet with an air working medium. Friction factors were determined for several sections located at the outlet of the fuel assembly. The distribution of the hydrodynamic characteristics of the coolant flow is visualized by cartograms of the axial velocity at the outlet of the fuel rod bundle, in the wide and narrow parts of the nozzle, as well as in the fragments of drain windows in the upper base plate. The flow of the coolant through the central displacer and pipe for conducting the coolant to the resistance thermometer is determined. According to the performed studies, the asymmetric nozzle, coolant sampling pipe of the resistance thermometer, and upper base plate are the essential parameters affecting the formation of the field structure for the axial flow velocity.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"57 - 61"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253526","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
Digital twins of nuclear energy complexes 核能综合体的数字双胞胎
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01128-1
A. Yu. Fedorovsky, S. O. Kiriyenko, A. A. Sypols
{"title":"Digital twins of nuclear energy complexes","authors":"A. Yu. Fedorovsky,&nbsp;S. O. Kiriyenko,&nbsp;A. A. Sypols","doi":"10.1007/s10512-024-01128-1","DOIUrl":"10.1007/s10512-024-01128-1","url":null,"abstract":"<div><p>The complex task of integrating various information, calculation, and simulation tools into a single system can be implemented using digital twins capable of optimizing design, engineering, and technological solutions, as well as supporting the ongoing operation of facilities. This article presents the results obtained within the development of integrating projects for the facilities of the “Proryv” project area, as well as discussing tools and solutions for creating digital twins, including integral mathematical models as a computational representation of the facility. The main directions for the further possible development of digital twins are considered relative to the construction of facilities, support for their operation, replication of digital twins themselves, and the search for innovative solutions that contribute to improvements in the quality both of the digital twins themselves and the actual created facilities.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"44 - 49"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253528","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
Application of laser technologies for dismantling the pipelines of MIR loop channels 应用激光技术拆除近红外环形通道管道
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-16 DOI: 10.1007/s10512-024-01132-5
R. E. Romanov, S. V. Gvozdev, I. A. Malyshkin, R. V. Maslennikov, D. D. Metliaev, A. V. Mochalov, M. V. Rzhevsky, A. G. Eshcherkin, A. Yu. Khaliapin, M. G. Kirdiashkin, Yu. N. Solovov, I. V. Borisov, R. A. Yashin
{"title":"Application of laser technologies for dismantling the pipelines of MIR loop channels","authors":"R. E. Romanov,&nbsp;S. V. Gvozdev,&nbsp;I. A. Malyshkin,&nbsp;R. V. Maslennikov,&nbsp;D. D. Metliaev,&nbsp;A. V. Mochalov,&nbsp;M. V. Rzhevsky,&nbsp;A. G. Eshcherkin,&nbsp;A. Yu. Khaliapin,&nbsp;M. G. Kirdiashkin,&nbsp;Yu. N. Solovov,&nbsp;I. V. Borisov,&nbsp;R. A. Yashin","doi":"10.1007/s10512-024-01132-5","DOIUrl":"10.1007/s10512-024-01132-5","url":null,"abstract":"<div><p>The article presents the results of using a multifunctional laser module for remote separation cutting of MIR reactor loop channels. The working conditions and parameters for cutting radioactive equipment are described. Alternative methods, as well as the risks associated with the considered method are analyzed.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"68 - 71"},"PeriodicalIF":0.4,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142253530","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
Effects of control rod movement parameters on the simulation of VVER-1200 rod ejection accidents 控制棒运动参数对 VVER-1200 控制棒弹射事故模拟的影响
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-12 DOI: 10.1007/s10512-024-01124-5
M. A. Zakharov, A. V. Kotsarev, M. P. Lizorkin, V. V. Morozov, B. E. Shumskiy
{"title":"Effects of control rod movement parameters on the simulation of VVER-1200 rod ejection accidents","authors":"M. A. Zakharov,&nbsp;A. V. Kotsarev,&nbsp;M. P. Lizorkin,&nbsp;V. V. Morozov,&nbsp;B. E. Shumskiy","doi":"10.1007/s10512-024-01124-5","DOIUrl":"10.1007/s10512-024-01124-5","url":null,"abstract":"<div><p>The article examines the effects of duration and movement mode of the control rod of the VVER-1200 control and protection system during its fast ejection from the core on the results of accident simulation. Two modes of movement are considered including uniform and equi-accelerated modes, in which the duration of the bottom-stop ejection varies from 0.01 to 5 s. The ejection of the control rod is simulated for reactor states of a full and minimum-controlled power, as well as with and without leakage for the first six 18-month VVER-1200 fuel campaigns. Calculations were carried out using the ATHLET/BIPR-VVER code (version 1.0). The performed studies demonstrated insignificant sensitivity of extreme fuel temperatures and departure-from-nucleate-boiling margin to ejection parameters. The approximated uniform movement of the control rod during 0.1 s of ejection is sufficiently conservative for use in the deterministic safety analysis of VVER nuclear power plants.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"20 - 26"},"PeriodicalIF":0.4,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201189","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
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade 方形级联多步骤方案中 95-97Mo 的浓缩和同位素改性钼的生产
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-12 DOI: 10.1007/s10512-024-01135-2
V. A. Palkin
{"title":"Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade","authors":"V. A. Palkin","doi":"10.1007/s10512-024-01135-2","DOIUrl":"10.1007/s10512-024-01135-2","url":null,"abstract":"<div><p>The paper considers the concentration of <sup>95–97</sup>Mo in a square cascade with large stage separation coefficients corresponding to gas centrifuges. Cascades were calculated using a method for varying the sections of partial stage streams and minimizing the deviation of calculated stage feeding streams from the specified one. A computational experiment on the multi-step separation of a molybdenum hexafluoride mixture was carried out. Isotopes of <sup>95–97</sup>Mo can be efficiently concentrated in a single square cascade. In streams depleted of these isotopes, isotopically modified molybdenum is accumulated for use as a structural material for fuel element claddings having improved thermophysical characteristics.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 1-2","pages":"84 - 90"},"PeriodicalIF":0.4,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201190","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 verification of the RING 2.0 software for calculating thermal-hydraulic characteristics of fuel assemblies with annular fuel elements 开发并验证 RING 2.0 软件，用于计算带有环形燃料元件的燃料组件的热液压特性
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-10 DOI: 10.1007/s10512-024-01119-2
V. V. Petrunin, M. A. Bolshuhin, A. N. Lepehin, A. S. Savinovskii
{"title":"Development and verification of the RING 2.0 software for calculating thermal-hydraulic characteristics of fuel assemblies with annular fuel elements","authors":"V. V. Petrunin,&nbsp;M. A. Bolshuhin,&nbsp;A. N. Lepehin,&nbsp;A. S. Savinovskii","doi":"10.1007/s10512-024-01119-2","DOIUrl":"10.1007/s10512-024-01119-2","url":null,"abstract":"<div><p>The paper describes the development and verification of the RING 2.0 software designed for thermal-hydraulic calculations of cores and fuel assemblies with annular fuel elements. Results from a set of experimental and theoretical studies carried out on the basis of a computational model embedded in code to verify the RING 2.0 software regarding the cores of research and isotope production reactors are presented.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"323 - 327"},"PeriodicalIF":0.4,"publicationDate":"2024-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201191","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 of an artificial neural network for a combined model of the uranium extraction process 为铀萃取工艺组合模型开发人工神经网络
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-06 DOI: 10.1007/s10512-024-01107-6
I. S. Nadezhdin, A. M. Emelyanov, S. N. Liventsov
{"title":"Development of an artificial neural network for a combined model of the uranium extraction process","authors":"I. S. Nadezhdin,&nbsp;A. M. Emelyanov,&nbsp;S. N. Liventsov","doi":"10.1007/s10512-024-01107-6","DOIUrl":"10.1007/s10512-024-01107-6","url":null,"abstract":"<div><p>Based on a conducted literature review, a training sample was compiled. The selected optimal parameters for training an artificial neural network included its structure, activation function, output layer transfer function, and the number of neurons in hidden layers. The results of calculations using the developed artificial neural network have an uncertainty of less than 1%, which confirms its suitability for creating a digital twin of a technological process.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"235 - 241"},"PeriodicalIF":0.4,"publicationDate":"2024-09-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201193","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
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests 在循环动力反应堆试验中形成 VVER 反应堆参数要求的方法
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-06 DOI: 10.1007/s10512-024-01118-3
V. I. Kuznetsov, A. S. Eremenko, E. A. Avdonina, K. Yu. Kurakin, P. E. Filimonov
{"title":"Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests","authors":"V. I. Kuznetsov,&nbsp;A. S. Eremenko,&nbsp;E. A. Avdonina,&nbsp;K. Yu. Kurakin,&nbsp;P. E. Filimonov","doi":"10.1007/s10512-024-01118-3","DOIUrl":"10.1007/s10512-024-01118-3","url":null,"abstract":"<div><p>The work was carried out as part of the computational and experimental justification of the operability of U and U‑Gd fuel rods of the VVER reactor in cycling power operating modes as part of the process of licensing domestically-produced fuel according to the requirements of Russian and foreign supervisory authorities. A methodology for forming the requirements for the rate of change in the local linear power of VVER reactors during tests in the research reactor simulating the cycling mode was developed.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"318 - 322"},"PeriodicalIF":0.4,"publicationDate":"2024-09-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201192","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
Innovative software package for calculating the neutron-physical characteristics of RBMK-1000 reactors via the multi-group Monte Carlo method using graphic processing units (GPUs) 利用图形处理器（GPU）通过多组蒙特卡洛法计算 RBMK-1000 反应堆中子物理特性的创新软件包
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-05 DOI: 10.1007/s10512-024-01114-7
I. E. Ivanov, S. A. Bychkov, N. A. Grushin, V. A. Varfolomeeva, V. E. Druzhinin
{"title":"Innovative software package for calculating the neutron-physical characteristics of RBMK-1000 reactors via the multi-group Monte Carlo method using graphic processing units (GPUs)","authors":"I. E. Ivanov,&nbsp;S. A. Bychkov,&nbsp;N. A. Grushin,&nbsp;V. A. Varfolomeeva,&nbsp;V. E. Druzhinin","doi":"10.1007/s10512-024-01114-7","DOIUrl":"10.1007/s10512-024-01114-7","url":null,"abstract":"<div><p>The present article reviews the innovative MNT-CUDA software package designed for engineering calculations of the neutron-physical characteristics of RBMK-1000 reactors according to the multi-group Monte Carlo method. An essential feature of the software is the ability to conduct multi-group fuel element calculations of the entire reactor volume with the restoration of in-core sensor data using the Monte Carlo method. Thanks to NVIDIA CUDA GPU parallel computing technology, a counting speed of about 0.2–1 billion neutron events per minute is achieved on a personal computer equipped with a state-of-engineering video card. The history of creating the software package from the first version to the latest at the moment, as well as some results of verification and certification are given. A brief information on the methods used in the software package is provided. The concept of building its complex architecture, the prospects for development, and the results of testing in the calculations of fast and uranium-water systems are set out.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"289 - 296"},"PeriodicalIF":0.4,"publicationDate":"2024-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201195","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
Chemical control of coolants in heavy-water systems of a PIK reactor PIK 反应堆重水系统冷却剂的化学控制
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-05 DOI: 10.1007/s10512-024-01113-8
T. V. Voronina
{"title":"Chemical control of coolants in heavy-water systems of a PIK reactor","authors":"T. V. Voronina","doi":"10.1007/s10512-024-01113-8","DOIUrl":"10.1007/s10512-024-01113-8","url":null,"abstract":"<div><p>The PIK research reactor includes circuits of heavy-water reflector and liquid regulation representing systems important for nuclear safety. Therefore, the issue of organizing the optimal water-chemical mode and chemical control of coolants for these two systems is relevant. The volume of chemical control for coolants of heavy water circuits was developed taking into account existing experience and the physicochemical characteristics of heavy water. In order to return heavy water to the heavy-water reflector circuit and reduce the dose load on laboratory personnel, a unique automated system of sampling and analysis was created for online monitoring of heavy water in the heavy-water reflector of the PIK reactor.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"283 - 288"},"PeriodicalIF":0.4,"publicationDate":"2024-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201197","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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