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Determining the Temperature Coefficient of Reactivity of the VVR-ts Reactor in the Operating Temperature Range VVR-ts反应堆在工作温度范围内反应性温度系数的确定
Q4 Energy Pub Date : 2022-12-01 DOI: 10.26583/npe.2022.4.02
Oleg Yur’evich Kochnov, D. A. Pakholik, Evgenij Valer’evich Nikulin, V. V. Kolesov
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引用次数: 0
The Steam-Hydrogen-Based Method for Reproducing Oxygen Thermodynamic Activity in Lead-Containing Alloys to Verify Oxygen Activity Sensors 基于蒸汽-氢的方法再现含铅合金中的氧热力学活性以验证氧活性传感器
Q4 Energy Pub Date : 2022-12-01 DOI: 10.26583/npe.2022.4.08
R. P. Sadovnichiy, Andrey Nikolayevich Skomorohov, Aleksandr Yur’evich Legkikh, R. Askhadullin, Valery Stanislavovich Lotov
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引用次数: 0
Benchmarking of the Results of Analytical and Experimental Studies of Complicated Heat and Mass Transfer in the Cavity of a High-Temperature Gas-Cooled Reactor 高温气冷堆腔内复杂传热传质分析与实验研究结果的对标
Q4 Energy Pub Date : 2022-12-01 DOI: 10.26583/npe.2022.4.04
D. V. Didenko, O. Nikanorov, S. Rogozhkin, A. Aksenov, Maksim N. Zhestkov, E. Shaporenko
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引用次数: 0
Method for Measuring the Local Mass of Uranium in Uranium-Aluminum Targets for 99Mo Generation 99Mo代铀铝靶中铀局部质量的测定方法
Q4 Energy Pub Date : 2022-12-01 DOI: 10.26583/npe.2022.4.10
V. Romanovskiy, Andrey Pavlovich Malkov, Alexandr Victorovich Kremer, Y. Kushnir, Dmitriy Anatolievich Leonenko, Alexander Anatolievich Leonenko
{"title":"Method for Measuring the Local Mass of Uranium in Uranium-Aluminum\u0000 Targets for 99Mo Generation","authors":"V. Romanovskiy, Andrey Pavlovich Malkov, Alexandr Victorovich Kremer, Y. Kushnir, Dmitriy Anatolievich Leonenko, Alexander Anatolievich Leonenko","doi":"10.26583/npe.2022.4.10","DOIUrl":"https://doi.org/10.26583/npe.2022.4.10","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72549939","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 Machine Learning Methods for Filling and Updating Nuclear Knowledge Databases 机器学习方法在核知识库填充与更新中的应用
Q4 Energy Pub Date : 2022-12-01 DOI: 10.26583/npe.2022.4.11
Victor Petrovich Tel’nov, Y. Korovin
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引用次数: 0
Examination of Fuel Elements Irradiated in the Reactor of the World’s First NPP After Long-Term Storage 世界首个核电站反应堆长期贮存后辐照燃料元件的检验
Q4 Energy Pub Date : 2022-09-01 DOI: 10.26583/npe.2022.3.10
S. Ivanov, S. Porollo, S. Shulepin, Y. Baranaev, V. Timofeev, Y. Kharizomenov
Examinations of fuel elements with two different fuel compositions, U-Mo+Mg and UO2+Mg, irradiated in the AM reactor after their long-term storage do not reveal any visible defects on the surface of their outer claddings. However, in the fuel elements with U-Mo fuel, an increase in the diameter of the outer cladding is observed. This is most noticeable in the upper part of the fuel element. Storage of the fuel elements with UO2 fuel for 15–22 years does not lead to a change in their diameter within the measurement accuracy. At the same time, metallographic studies have shown that on the external surface of the outer cladding and the internal surface of the inner cladding of the fuel elements with U-Mo+Mg and UO2+Mg fuel compositions, after long-term storage, defects are observed in the form of intergranular and irregular frontal corrosion, pits and pittings up to 20 µm deep. No interaction is found at the points of contact between the fuel claddings and the fuel composition of the layers. There is no noticeable decrease in the thickness of the outer and inner claddings of the fuel elements after long-term storage, nor does the thickness of the claddings at the locations of defects go beyond its minimum initial value, taking into account the technological tolerance for variations in thickness. It is noteworthy, however, that cracks are found in both types of fuel elements both in the fuel grains and in the magnesium matrix. As a result of long-term storage of the fuel elements with U-Mo fuel for 45–55 years, the mechanical properties of their outer claddings gradually degrade, due to which the plasticity of the cladding is significantly reduced.
对两种不同燃料成分的燃料元件(U-Mo+Mg和UO2+Mg)在长期储存后在AM反应堆中辐照的检查未发现其外包层表面有任何可见的缺陷。然而,在使用铀钼燃料的燃料元件中,可以观察到外包层直径的增加。这在燃料元件的上部最为明显。使用UO2燃料的燃料元件储存15-22年不会导致其直径在测量精度范围内发生变化。同时,金相研究表明,在U-Mo+Mg和UO2+Mg燃料成分的燃料元件的外包层外表面和内包层内表面,经过长期存放后,出现了晶间和不规则的正面腐蚀,凹坑和点蚀深度可达20µm。在燃料包壳和各层燃料组成之间的接触点没有发现相互作用。考虑到厚度变化的技术公差,长期储存后燃料元件的内外包层厚度没有明显下降,缺陷位置的包层厚度也没有超过其最小初始值。然而,值得注意的是,在两种类型的燃料元件中,在燃料颗粒和镁基体中都发现了裂纹。铀钼燃料元件长期存放45 ~ 55年,其外包层的力学性能逐渐退化,包层的塑性明显降低。
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引用次数: 0
Increasing the Efficiency of the Fuel Cladding Failure Detection System with Respect to Gas in Liquid-Metal Fast Breeder Reactors 提高液态金属快堆中气体燃料包壳失效检测系统的效率
Q4 Energy Pub Date : 2022-09-01 DOI: 10.26583/npe.2022.3.08
A. A. Kudryaev, D. A. Lukyanov, Sergey Alexandrovich Guryev, Margarita Igorevna Steporzhinskaya
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引用次数: 0
Three-Dimensional Models and Complimentary Geometry for Dose Evaluation in NG-24MT Based Neutron Radiotherapy Cabinet 基于NG-24MT的中子放疗柜剂量评估的三维模型和互补几何
Q4 Energy Pub Date : 2022-09-01 DOI: 10.26583/npe.2022.3.14
Alexander Evgenievich Chernukha, V. Saburov, Alevtina Igorevna Adarova, A. Solovev, Yana Vladimirovna Kizilova, S. Koryakin
{"title":"Three-Dimensional Models and Complimentary Geometry for Dose Evaluation in NG-24MT Based Neutron Radiotherapy Cabinet","authors":"Alexander Evgenievich Chernukha, V. Saburov, Alevtina Igorevna Adarova, A. Solovev, Yana Vladimirovna Kizilova, S. Koryakin","doi":"10.26583/npe.2022.3.14","DOIUrl":"https://doi.org/10.26583/npe.2022.3.14","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82477837","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Influence of the Spatial Grid Type on the Result of Calculating the Neutron Fields in the Nuclear Power Plant Shielding 空间网格类型对核电厂屏蔽中子场计算结果的影响
Q4 Energy Pub Date : 2022-09-01 DOI: 10.26583/npe.2022.3.13
O. Nikolaeva, S. Gaifulin, L. Bass, Denis Vitalievich Dmitriev, N.A. Nikolaev
The paper considers the influence of the spatial grid type on the result of solving the equation of neutron transport in the nuclear power plant (NPP) shielding. Neutron fields were calculated in a realistic model of a liquid metal cooled fast neutron tank reactor with an integral equipment layout. Structured cubic and unstructured hexahedral grids (pmsnsys and FRIGATE codes) and unstructured tetrahedral and prismatic grids (RADUGA T code) are used. Limiting values of the group fluxes averaged over the material zones for refined grids have been obtained. It has been shown that the calculation results depend on the type of approximation for the curvilinear inner boundaries between the material zones rather than on the grid cell type (cube, hexahedron, tetrahedron, prism). Using “toothed” approximations for curvilinear boundaries leads to an increase in the area of the boundaries, as well as to the neutron flux refraction condition arising on them. These effects lead to an upward bias in the transport equation solution, and for all energy groups. Conclusion. When solving an equation of neutron transport in the NPP shielding by a grid technique, it is necessary to use grids other than leading to “toothed” approximations of the inner boundaries. Tetrahedral or prismatic grids, or grids of arbitrary hexahedrons can be recommended, as well as composite grids in which cubic cells are located inside the material zone, and hexahedron cells are located near the zone boundary.
本文考虑了空间网格类型对核电厂屏蔽层中子输运方程求解结果的影响。对采用整体式设备布置的液态金属冷却快中子槽式反应堆进行了中子场计算。采用结构化立方网格和非结构化六面体网格(pmsnsys和FRIGATE代码)和非结构化四面体网格和棱镜网格(RADUGA T代码)。得到了精细化网格在材料区域上平均的群通量的极限值。结果表明,计算结果取决于材料区域间曲线内边界的近似类型,而不是取决于网格单元类型(立方体、六面体、四面体、棱镜)。对曲线边界使用“齿状”近似会导致边界面积的增加,以及在边界上产生的中子通量折射条件的增加。这些效应导致输运方程的解有一个向上的偏置,对所有的能量群都是如此。结论。在用网格技术求解核电站屏蔽中中子输运方程时,有必要使用网格,而不是导致内部边界的“齿状”近似。推荐使用四面体网格或棱柱体网格,或任意六面体网格,以及立方体单元位于材料区域内,六面体单元位于区域边界附近的复合网格。
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引用次数: 0
Analysis of the Efficiency of Training for Foreign Students in the Field of Non-Power Applications of Nuclear Technologies 核技术非动力应用领域外国留学生培训效率分析
Q4 Energy Pub Date : 2022-09-01 DOI: 10.26583/npe.2022.3.15
A. Panov, Gennadij Vasil’evich Kozmin
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引用次数: 0
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Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
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