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Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors 研究对 VVER-1200 反应堆使用两组加速预防性保护的可能性
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-15 DOI: 10.1007/s10512-024-01092-w
A. A. Dubov, E. F. Mikailov, S. S. Gusev
{"title":"Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors","authors":"A. A. Dubov,&nbsp;E. F. Mikailov,&nbsp;S. S. Gusev","doi":"10.1007/s10512-024-01092-w","DOIUrl":"10.1007/s10512-024-01092-w","url":null,"abstract":"<div><p>Considering present opportunities for modernizing accelerated preventive protection (APP) for VVER-1200 reactors, a methodology for selecting two APP groups is presented. Using the described methodology and selection criteria, two APP groups (APP1 and APP2) are selected for modes of disabled RCPSs and two electric feeding pumps during operation at a rated power level. The study represents an important stage in the modernization of the safety algorithm, i.e., accelerated preventive protection of the reactor. The results presented in the article are relevant for research and development purposes, as well as for safety analysis.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"128 - 134"},"PeriodicalIF":0.4,"publicationDate":"2024-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141645608","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
Simulation of NPP cable gland leakage monitoring 核电厂电缆接头泄漏监测模拟
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-11 DOI: 10.1007/s10512-024-01105-8
S. M. Slobodyan, S. P. Vashchuk
{"title":"Simulation of NPP cable gland leakage monitoring","authors":"S. M. Slobodyan,&nbsp;S. P. Vashchuk","doi":"10.1007/s10512-024-01105-8","DOIUrl":"10.1007/s10512-024-01105-8","url":null,"abstract":"<div><p>The paper analyzes a nano-scale atomic-molecular model for filling a cable gland with sealant. The dependence of the NPP cable gland state assessment on the parameters of the sealant movement model is demonstrated. The simulation gives a satisfactory convergence with the known experimental and theoretical results.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"224 - 227"},"PeriodicalIF":0.4,"publicationDate":"2024-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608787","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
Accounting for the reference data correlation when determining the calculation error using the maximum likelihood method 在使用最大似然法确定计算误差时考虑参考数据的相关性
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-11 DOI: 10.1007/s10512-024-01104-9
A. M. Degtyarev, O. A. Seryanina
{"title":"Accounting for the reference data correlation when determining the calculation error using the maximum likelihood method","authors":"A. M. Degtyarev,&nbsp;O. A. Seryanina","doi":"10.1007/s10512-024-01104-9","DOIUrl":"10.1007/s10512-024-01104-9","url":null,"abstract":"<div><p>Given the assumption of normal distribution, the determination of the calculation error for the correlation of the initial reference data is considered. In this case, it is proposed to use the maximum likelihood method with a non-diagonal covariance matrix. The relationship of calculation deviations from the reference data is assumed to be described by known correlation coefficients. Techniques for constructing the average value, error variance, and distribution of its probability are described. The determination of the correlation coefficient for <i>k</i><sub>eff</sub> is considered using two consecutive campaigns of the PIK reactor. Possible directions for future modification of the methodology are discussed.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"218 - 223"},"PeriodicalIF":0.4,"publicationDate":"2024-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608786","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
Cryogenic mesitylene-based moderator as an optimum solution for use in a DARIA compact neutron source 低温间二甲苯慢化剂是用于 DARIA 紧凑型中子源的最佳解决方案
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-11 DOI: 10.1007/s10512-024-01100-z
M. V. Bulavin, K. A. Mukhin, A. D. Rogov, A. A. Hassan
{"title":"Cryogenic mesitylene-based moderator as an optimum solution for use in a DARIA compact neutron source","authors":"M. V. Bulavin,&nbsp;K. A. Mukhin,&nbsp;A. D. Rogov,&nbsp;A. A. Hassan","doi":"10.1007/s10512-024-01100-z","DOIUrl":"10.1007/s10512-024-01100-z","url":null,"abstract":"<div><p>The paper presents the results of neutron-physical calculations for determining the optimum configuration of materials for use as a cryogenic moderator in a DARIA university-grade compact neutron source. It is shown that a cryogenic moderator based on a solid frozen mesitylene of a certain configuration may represent the optimum source of cold neutrons for studying the structure and properties of substances by neutron-physical methods in the DARIA neutron source.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"189 - 194"},"PeriodicalIF":0.4,"publicationDate":"2024-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608839","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
Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U 从 232、234、236U 中提纯后处理六氟化铀的气体离心机双级联方案
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01097-5
V. A. Palkin
{"title":"Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U","authors":"V. A. Palkin","doi":"10.1007/s10512-024-01097-5","DOIUrl":"10.1007/s10512-024-01097-5","url":null,"abstract":"<div><p>The paper considers features of purification the reprocessed uranium hexafluoride from <sup>232, 234, 236</sup>U in two cascades of gas centrifuges with additional feeding streams of waste uranium hexafluoride to the product stages of the cascades. The effective purification from <sup>236</sup>U in the first cascade is carried out at a <sup>235</sup>U concentration of less than 20% in long cascades having a large number of stages. The parameters of the second cascade that significantly reduce the concentration of <sup>232, 234</sup>U in the wastes were determined. As a result of the reduction with waste uranium hexafluoride, this stream ensures a commercial low-enriched product to meet the requirements of the ASTM C996-20 specification established for enriched industrial uranium hexafluoride.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"166 - 172"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585112","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
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment 切尔诺贝利核电站和福岛第一核电站（日本）事故对农业和环境影响的比较分析
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01101-y
S. V. Fesenko
{"title":"A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment","authors":"S. V. Fesenko","doi":"10.1007/s10512-024-01101-y","DOIUrl":"10.1007/s10512-024-01101-y","url":null,"abstract":"<div><p>The article presents a comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi NPPs. Both accidents are demonstrated to have had severe effects for agriculture and natural environment. The consequences of radiation accidents are shown to have been significantly impacted by the composition of the radionuclide release during the accident, the season of the year, and the natural features of the contaminated regions.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"195 - 205"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585116","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
Evaluation of technological uncertainties using the sensitivity to nuclear data 利用核数据敏感性评估技术不确定性
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-10 DOI: 10.1007/s10512-024-01103-w
A. A. Ryzhkov, G. V. Tikhomirov, M. Yu. Ternovykh, A. S. Gerasimov
{"title":"Evaluation of technological uncertainties using the sensitivity to nuclear data","authors":"A. A. Ryzhkov,&nbsp;G. V. Tikhomirov,&nbsp;M. Yu. Ternovykh,&nbsp;A. S. Gerasimov","doi":"10.1007/s10512-024-01103-w","DOIUrl":"10.1007/s10512-024-01103-w","url":null,"abstract":"<div><p>The paper presents an assessment of the effect caused by technological uncertainties on <i>k</i><sub>eff</sub> using the example of the test problem for a MET1000 fast sodium reactor with metal fuel. It is proposed to perform this assessment using nuclear sensitivity factors by random sampling or direct perturbation without requiring multiple calculations. The TSUNAMI-3D module of the SCALE program was used to analyze the sensitivity to nuclear data uncertainty. The obtained constant and technological uncertainties based on ENDF/B VII.1 equal 1.15 and 0.6%, respectively. The result was verified using direct perturbation. It is shown that a significant proportion of the technological uncertainties can be determined within the framework of the proposed evaluation method.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"211 - 217"},"PeriodicalIF":0.4,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585113","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
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
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