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Demand of fusion energy for tritium and the possibility of its production in nuclear reactors 聚变能对氚的需求以及在核反应堆中生产氚的可能性
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01099-3
B. V. Ivanov, S. S. Ananev
{"title":"Demand of fusion energy for tritium and the possibility of its production in nuclear reactors","authors":"B. V. Ivanov,&nbsp;S. S. Ananev","doi":"10.1007/s10512-024-01099-3","DOIUrl":"10.1007/s10512-024-01099-3","url":null,"abstract":"<div><p>The annual consumption of tritium in a fusion reactor is estimated at ~56 kg per 1 GW. Its amount depends on the power of the reactor, plasma parameters, and the technologies used. Tritium can be produced in nuclear reactors to form an initial margin. The present article analyzes the demand for tritium during the future development of fusion energy. It is shown that tritium demand under various scenarios exceeds current production capabilities and margins. An overview of tritium production in PWRs (USA) is presented. Lithium absorbing rods and stages of their technological implementation are described. The production of tritium in a reactor limited to 1.5 kg/year is demonstrated to cause no effect on operation or safety. The introduction of such technologies, which have been worked out over a period of around 15 years, is possible in both VVER and RBMK reactors.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"183 - 188"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585109","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 6–10 wt% of gadolinium oxide 含 6-10 wt%氧化钆的 VVER 铀钆燃料芯块的热物理性质
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01096-6
A. V. Fedotov, A. V. Lysikov, M. A. Lutkov
{"title":"Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide","authors":"A. V. Fedotov,&nbsp;A. V. Lysikov,&nbsp;M. A. Lutkov","doi":"10.1007/s10512-024-01096-6","DOIUrl":"10.1007/s10512-024-01096-6","url":null,"abstract":"<div><p>The study aims to determine the thermophysical properties of uranium-gadolinium oxide fuel pellets with 6, 7, 9, and 10 wt% of gadolinium oxide for the verification of the Start-4A calculation code. The determined properties will help to clarify calculations on the behavior of fuel elements in normal and emergency operational conditions during operability substantiation and licensing of the fuel for VVER reactor plants. Experimental dependencies of thermal expansion, specific thermal capacity at a constant pressure and thermal diffusivity were obtained along with the calculated dependence of thermal conductivity on the temperature for the fuels with various contents of Gd<sub>2</sub>O<sub>3</sub>. In comparison with uranium dioxide, the main contribution to an almost twofold decrease in thermal conductivity at an increase in the gadolinium content is made by the thermal diffusivity of uranium-gadolinium fuel.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"157 - 165"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585111","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 of a square cascade using the bee colony algorithm 利用蜂群算法计算方形级联
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01106-7
V. A. Palkin
{"title":"Calculation of a square cascade using the bee colony algorithm","authors":"V. A. Palkin","doi":"10.1007/s10512-024-01106-7","DOIUrl":"10.1007/s10512-024-01106-7","url":null,"abstract":"<div><p>A method for calculating a square cascade with an arbitrary number of external streams by varying the sections of partial-stage streams and minimizing the deviation of the calculated-stage feeding streams from the specified stream was developed. The method applies the bee colony algorithm, which minimizes the deviation of streams to ensure the required accuracy of determining cascade parameters. On the basis of the computational experiment on the separation of molybdenum hexafluoride, the method demonstrated high efficiency when calculating the concentration of isotopes with the lowest and highest mass numbers.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"228 - 233"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585114","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
Method for determining the realistic size of a crack in a containment in the case of a severe accident 严重事故情况下确定安全壳裂缝实际大小的方法
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01095-7
O. V. Goryunov
{"title":"Method for determining the realistic size of a crack in a containment in the case of a severe accident","authors":"O. V. Goryunov","doi":"10.1007/s10512-024-01095-7","DOIUrl":"10.1007/s10512-024-01095-7","url":null,"abstract":"<div><p>Calculations of severe accidents performed for level 2 probabilistic risk analysis (PRA-2) require the relevant leakage parameters such as location, area, flow rate, etc. Since the pressure of the medium at which the leakage occurs is probabilistic, a series of variant calculations of a severe accident is performed for the PRA‑2. However, when postulating the occurrence of a leakage, determining its size and location remains problematic. In this regard, an approach is proposed for reducing the number of variant calculations of severe accidents for the PRA‑2 to obtain its realistic results. According to conservative assumptions, a single through crack in the most stressed area of the lining is postulated, whose behavior will determine the ultimate state of the containment. The initial crack size corresponds to the leakage of the medium during the commissioning tests of the containment. Leakage parameters can thus be determined based on the assessment of the stress-strain state of the containment lining, while the ultimate state is established on the basis of the linear fracture mechanics.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"148 - 156"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585110","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
Control of pipeline thermal displacements using a computer vision system with a chessboard 利用带棋盘的计算机视觉系统控制管道热位移
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-08 DOI: 10.1007/s10512-024-01094-8
E. L. Matveev, A. L. Matveev, M. S. Cherkasova, A. Yu. Mishenin
{"title":"Control of pipeline thermal displacements using a computer vision system with a chessboard","authors":"E. L. Matveev,&nbsp;A. L. Matveev,&nbsp;M. S. Cherkasova,&nbsp;A. Yu. Mishenin","doi":"10.1007/s10512-024-01094-8","DOIUrl":"10.1007/s10512-024-01094-8","url":null,"abstract":"<div><p>The article presents the results of developing a fragment of a thermal displacement control system, writing the corresponding software for measuring the linear displacement of the monitored equipment and pipelines, and analyzing the obtained results for assessing the technical state and cyclic strength of the monitored equipment as a means of managing the resource characteristics of the controlled object. The measurement uncertainty was evaluated. Taking into account the influence of various factors, such as illumination, the degree of filling the image with the target, the distance from the video camera to the target, as well as the direction and dimensions of displacements and vibration, the volume of test checks was formed using 780 tests. In the course of the analysis, the relative error in measuring displacements taking vibrations into account was revealed to be no more than 5%.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"142 - 147"},"PeriodicalIF":0.4,"publicationDate":"2024-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141567218","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
The role and position of HTGR reactor technology in the development of the Russian energy 高温热核反应堆技术在俄罗斯能源发展中的作用和地位
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-02 DOI: 10.1007/s10512-024-01093-9
E. V. Rodionova, A. L. Balanin, A. V. Grol, V. A. Nevinitsa, P. A. Fomichenko
{"title":"The role and position of HTGR reactor technology in the development of the Russian energy","authors":"E. V. Rodionova,&nbsp;A. L. Balanin,&nbsp;A. V. Grol,&nbsp;V. A. Nevinitsa,&nbsp;P. A. Fomichenko","doi":"10.1007/s10512-024-01093-9","DOIUrl":"10.1007/s10512-024-01093-9","url":null,"abstract":"<div><p>The article considers the possibility of using high-temperature gas-cooled reactor (HTGR) technology for the needs of industrial heating, primarily for enterprises that require high-potential heat in technological processes and operate in a continuous cycle mode. The integral demand for the thermal power of HTGRs for the development of the metallurgical, petrochemical, chemical, and processing industries until 2100 is estimated. The potential of using thermal power for the needs of industrial hydrogen production by the method of the methane steam conversion is estimated. In addition to saving the natural resources of the hydrocarbon fuel currently used for heating, the introduction of HTGRs will ameliorate the environmental situation associated with emissions of pollutants and greenhouse gases, as well as reducing the evaporation of purified water.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"135 - 141"},"PeriodicalIF":0.4,"publicationDate":"2024-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141525216","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
Formation of design and operational databases on the reliability of equipment at Nuclear Fuel Cycle facilities 建立核燃料循环设施设备可靠性设计和运行数据库
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-20 DOI: 10.1007/s10512-024-01086-8
E. A. Shiverskiy, A. N. Terekhin, S. S. Andreev, A. S. Nikulin
{"title":"Formation of design and operational databases on the reliability of equipment at Nuclear Fuel Cycle facilities","authors":"E. A. Shiverskiy,&nbsp;A. N. Terekhin,&nbsp;S. S. Andreev,&nbsp;A. S. Nikulin","doi":"10.1007/s10512-024-01086-8","DOIUrl":"10.1007/s10512-024-01086-8","url":null,"abstract":"<div><p>The uniqueness of the nuclear fuel cycle facilities and their equipment, which must be adjusted to the specific conditions of manufacturing and (or) reprocessing the fuel of a particular reactor type in each case, complicates the application of traditional methods for assessing reliability and safety, thus relying on the availability of a significant operating experience. As a result, at the design stage, the reliability level of such equipment is determined by the available data on the reliability of analog elements. Following completion of commissioning of a nuclear fuel cycle facility, the regulatory requirements demand the updating of reliability and safety calculations to bring them in line with the actual state of the facility based on the results of the construction, commissioning, as well as pilot- and pilot-industrial operation. The article presents a universal method for accounting for the statistics of equipment operation at a high level of reliability in the absence of representative samples during the first years of its operation, which is compensated by the use of prior information within the framework of the Bayesian approach. The simulation of the time between failures is demonstrated using the synthesis of the prior information and the results of prototype bench tests for 5 years.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"86 - 96"},"PeriodicalIF":0.4,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141508850","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
Increased sensitivity of fuel cladding failure detection 提高燃料包层故障检测的灵敏度
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-20 DOI: 10.1007/s10512-024-01089-5
A. B. Tereshchenko, E. I. Golubev
{"title":"Increased sensitivity of fuel cladding failure detection","authors":"A. B. Tereshchenko,&nbsp;E. I. Golubev","doi":"10.1007/s10512-024-01089-5","DOIUrl":"10.1007/s10512-024-01089-5","url":null,"abstract":"<div><p>The present paper considers the processes occurring in a failed fuel element during fuel cladding failure detection in the mast sipping system of the refueling machine. The time taken for water and fission gas products to leak from a failed fuel element during its lifting was estimated depending on the size of the defect. A period of 10–12 min exposure prior to bubbling was demonstrated to be applicable for detecting defects with a size of about 30 μm. The sizes of gas bubbles leaving the fuel element during the failure detection were estimated along with their rate of ascent. An algorithm for conducting fuel element failure detection that increases the sensitivity of the method without extending the refueling is proposed.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"115 - 119"},"PeriodicalIF":0.4,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141529791","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
Debatable issues on the derivation of the separation potential for multicomponent mixtures 多组分混合物分离电位推导的争议问题
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-10 DOI: 10.1007/s10512-024-01081-z
A. Yu. Smirnov, G. A. Sulaberidze
{"title":"Debatable issues on the derivation of the separation potential for multicomponent mixtures","authors":"A. Yu. Smirnov,&nbsp;G. A. Sulaberidze","doi":"10.1007/s10512-024-01081-z","DOIUrl":"10.1007/s10512-024-01081-z","url":null,"abstract":"<div><p>The paper analyzes the assumptions relied upon when deriving the general form of the separation potential for multicomponent mixtures. The complexity of applying the general form for evaluating the number of separating elements in a centrifuge cascade without performing calculations is demonstrated. Its potential application for other methods characterized by high selectivity for individual components of the separated mixture is discussed.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"55 - 60"},"PeriodicalIF":0.4,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141363522","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
Determination of separation power for the separation of a multicomponent isotope mixture 确定分离多组分同位素混合物的分离能力
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-10 DOI: 10.1007/s10512-024-01080-0
V. A. Palkin
{"title":"Determination of separation power for the separation of a multicomponent isotope mixture","authors":"V. A. Palkin","doi":"10.1007/s10512-024-01080-0","DOIUrl":"10.1007/s10512-024-01080-0","url":null,"abstract":"<div><p>Aspects of separation potentials for a multicomponent mixture of isotopes are considered. In order to separate isotopes of reprocessed uranium and germanium in cascades with high separation factors corresponding to gas centrifuges, a computational experiment was carried out. The application of potentials for calculating the separation power of elements, stages, and cascades is analyzed. Potentials that provide a satisfactory assessment of the actual separation power for the stages and the cascade, thus determining the costs of the separation work, are established. This characteristic, along with the separation power of the element, is virtually independent of the used potential type.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"47 - 54"},"PeriodicalIF":0.4,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141362326","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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