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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
Assessment of the state of water bodies in the territory of a decommissioned uranium mining enterprise 退役铀矿企业境内水体状况评估
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-05 DOI: 10.1007/s10512-024-01117-4
T. N. Lashchenova, Iu. K. Gubanova, L. E. Karl, E. I. Kaygorodov
{"title":"Assessment of the state of water bodies in the territory of a decommissioned uranium mining enterprise","authors":"T. N. Lashchenova,&nbsp;Iu. K. Gubanova,&nbsp;L. E. Karl,&nbsp;E. I. Kaygorodov","doi":"10.1007/s10512-024-01117-4","DOIUrl":"10.1007/s10512-024-01117-4","url":null,"abstract":"<div><p>An assessment of the radioecological state of water bodies on the territory of the uranium mining enterprise represented by the decommissioned Almaz Scientific and Production Association (LPO Almaz) uranium mining plant located in the town of Lermontov and in the adjacent residential area was carried out. Water bodies represent a critical factor for characterization of the radiation factor in terms of its impact on the population. After measuring the content of natural radionuclides in water and bottom sediments, the current radioecological state of water bodies as a whole was assessed. The content of natural radionuclides in water was estimated by multiplying the excess of the intervention level for each radionuclide present in a significant amount; for several radionuclides, the summarized ratios of specific activity to the corresponding level of intervention were used. The content of natural radionuclides in bottom sediments was estimated according to the effective specific activity of solid materials. A conservative average annual effective dose potential for the population in the residential area due to water bodies was calculated. Radium-226 was identified as the main radionuclide forming a dose load of internal exposure due to water bodies of the residential area in the immediate vicinity of the decommissioned LPO Almaz plant. Based on this radionuclide, an individual potential radiation risk to public health was calculated for recreational and agricultural modes of water use.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"310 - 317"},"PeriodicalIF":0.4,"publicationDate":"2024-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201194","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
Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors 快中子反应堆乏核燃料后处理湿法冶金技术的实验测试结果
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-09-05 DOI: 10.1007/s10512-024-01121-8
D. S. Shlyazhko, S. G. Terentev, K. N. Dvoeglazov, V. L. Sofronov
{"title":"Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors","authors":"D. S. Shlyazhko,&nbsp;S. G. Terentev,&nbsp;K. N. Dvoeglazov,&nbsp;V. L. Sofronov","doi":"10.1007/s10512-024-01121-8","DOIUrl":"10.1007/s10512-024-01121-8","url":null,"abstract":"<div><p>Results of experiments to test the modes of plutonium and neptunium displacement re-extraction with a nitrate solution of uranium (VI) are presented. The developed method of plutonium displacement re-extraction was tested at the refining extraction and crystallization facility of JSC SChC as part of the comprehensive program “Development of equipment, technologies, and scientific research in the field of nuclear energy use in the Russian Federation”. Due to a high accumulation of plutonium in the fuel of fast reactors, the main task of plutonium re-extraction consists in ensuring the re-extract ratio of Pu / (Pu + U) specified by the manufacturers of oxide fuel. According to the results of the performed tests, the developed method of plutonium displacement re-extraction with a solution of uranyl (VI) nitrate allows uranium, plutonium, and neptunium to be re-extracted in the ratio specified by fuel manufacturers. In this case, the completeness of plutonium extraction into the re-extract and its purification according to the proposed method are comparable to the results obtained in the process of reductive plutonium re-extraction.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"333 - 337"},"PeriodicalIF":0.4,"publicationDate":"2024-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201196","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 meteorological parameters on the intensity of tritium emission from spray cooling ponds 气象参数对喷雾冷却池氚排放强度的影响
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-08-27 DOI: 10.1007/s10512-024-01116-5
A. A. Ekidin, K. L. Antonov, M. E. Vasyanovich, D. D. Desyatov
{"title":"Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds","authors":"A. A. Ekidin,&nbsp;K. L. Antonov,&nbsp;M. E. Vasyanovich,&nbsp;D. D. Desyatov","doi":"10.1007/s10512-024-01116-5","DOIUrl":"10.1007/s10512-024-01116-5","url":null,"abstract":"<div><p>An algorithm for estimating tritium emission during the evaporation of water from spray cooling ponds of nuclear power plants is considered. The factors determining the intensity of evaporation and intake of tritium into the atmospheric air are analyzed. For the considered meteorological and technological factors of area source operation, the intensity of tritium emission averages 6.2 Bq/h from each 1·m<sup>2</sup> of the spray cooling pond area per each 1 Bq/L of specific water activity. The possibility of regulating the emission activity is demonstrated taking into account the data of controlled technological parameters for the water-cooling system of spray cooling ponds and the meteorological parameters of the atmosphere in the NPP location area.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"302 - 309"},"PeriodicalIF":0.4,"publicationDate":"2024-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142201198","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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