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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
Reduction of the erbium content in RBMK-1000 fuel 减少 RBMK-1000 燃料中的铒含量
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-10 DOI: 10.1007/s10512-024-01075-x
Yu. V. Alimov, A. V. Kaplienko, P. B. Kuznetsov, I. M. Rozhdestvenskiy, A. V. Slobodchikov, V. K. Davydov, A. P. Zhirnov, S. S. Lebedev
{"title":"Reduction of the erbium content in RBMK-1000 fuel","authors":"Yu. V. Alimov,&nbsp;A. V. Kaplienko,&nbsp;P. B. Kuznetsov,&nbsp;I. M. Rozhdestvenskiy,&nbsp;A. V. Slobodchikov,&nbsp;V. K. Davydov,&nbsp;A. P. Zhirnov,&nbsp;S. S. Lebedev","doi":"10.1007/s10512-024-01075-x","DOIUrl":"10.1007/s10512-024-01075-x","url":null,"abstract":"<div><p>The paper presents the results of a calculation study connected with the composition of RBMK-1000 fuel having a reduced erbium content. The computational studies were carried out using SADCO software systems (developed by JSC “NIKIET”) and MCU-RBMK (developed by NRC “Kurchatov Institute”). The studies include calculations of a fuel cell with various compositions of uranium-erbium fuel and a RBMK-1000 reactor under fuel-loading conditions involving a reduced erbium content. The conversion of RBMK-1000 to a fuel having a reduced erbium content ensures the neutron-physical characteristics and volumes of accumulating commercial <sup>60</sup>Co to be maintained within operational limits under conditions of extending the reactor service life for more than 50 years.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"12 - 19"},"PeriodicalIF":0.4,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141365755","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
Integral experiments with a cylindrical multiplying system of metal plutonium 金属钚圆柱倍增系统的积分实验
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-10 DOI: 10.1007/s10512-024-01076-w
V. A. Adarchenko, S. A. Andreev, S. S. Besov, A. A. Vaivod, D. V. Khmelnitsky, A. A. Yudov
{"title":"Integral experiments with a cylindrical multiplying system of metal plutonium","authors":"V. A. Adarchenko,&nbsp;S. A. Andreev,&nbsp;S. S. Besov,&nbsp;A. A. Vaivod,&nbsp;D. V. Khmelnitsky,&nbsp;A. A. Yudov","doi":"10.1007/s10512-024-01076-w","DOIUrl":"10.1007/s10512-024-01076-w","url":null,"abstract":"<div><p>The paper presents the results of critical, correlation, and spectral precision experiments carried out at the FKBN‑2 assembly machine using a cylindrical multiplying system made of low-background α‑phase plutonium. In the experiments, the critical state of the multiplying system was determined, the characteristics of non-stationary prompt neutron processes were investigated, and the number of nuclear reactions in the detectors was measured at a controlled power level of the multiplying system. After constructing a benchmark model for the multiplying system, a computational simulation of integral experiments was carried out. Based on the experimental results, the average lifetime of prompt neutrons and the effective fraction of delayed neutrons for the multiplying system were determined. The obtained results can be used to verify the codes of neutron-physics and refine neutron constants.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"20 - 26"},"PeriodicalIF":0.4,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141363809","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 large-scale purified inert atmosphere cells for the pyroprocessing treatment of spent nuclear fuel 开发用于乏核燃料热处理的大规模净化惰性气氛室
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-06-10 DOI: 10.1007/s10512-024-01078-8
I. V. Kuzmin, A. Y. Leshchenko, A. V. Nosov, V. P. Smirnov, R. N. Shamsutdinov, Y. S. Mochalov, L. P. Sukhanov
{"title":"Development of large-scale purified inert atmosphere cells for the pyroprocessing treatment of spent nuclear fuel","authors":"I. V. Kuzmin,&nbsp;A. Y. Leshchenko,&nbsp;A. V. Nosov,&nbsp;V. P. Smirnov,&nbsp;R. N. Shamsutdinov,&nbsp;Y. S. Mochalov,&nbsp;L. P. Sukhanov","doi":"10.1007/s10512-024-01078-8","DOIUrl":"10.1007/s10512-024-01078-8","url":null,"abstract":"<div><p>The paper addresses the development of prototype large-scale purified inert atmosphere cells for testing equipment used in the pyrochemical treatment of spent nuclear fuel from fast neutron reactors. In addition, design peculiarities of the cells are discussed along with a presentation of preliminary results of tests on the generation and maintenance of an inert atmosphere of required quality in them.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"34 - 39"},"PeriodicalIF":0.4,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141362170","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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