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Prospects for fusion neutron sources in the Russian nuclear power industry 俄罗斯核能工业聚变中子源的前景
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-23 DOI: 10.1007/s10512-024-01098-4
S. S. Ananev, A. V. Golubeva
{"title":"Prospects for fusion neutron sources in the Russian nuclear power industry","authors":"S. S. Ananev,&nbsp;A. V. Golubeva","doi":"10.1007/s10512-024-01098-4","DOIUrl":"10.1007/s10512-024-01098-4","url":null,"abstract":"<div><p>Since 2021, a comprehensive program comprising five projects has been implemented by the Rosatom State Corporation in the Russian Federation. Of these, the project entitled “Development of controlled fusion and innovative plasma technologies” is scientifically supervised by NRC Kurchatov Institute. The program envisages a development of the concept of a hybrid reactor plant that combines fusion and fission technologies. As well as presenting an overview of the feasibility, functions, and parameters of planned fusion neutron sources, the paper outlines the development concept of the hybrid system and prospects for its implementation as a means of expanding the fuel base and recycling high-level wastes. An analysis of target indicators is provided.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"173 - 182"},"PeriodicalIF":0.4,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141770907","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
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection 使用加油机桅杆吸入系统检测运行中燃料包层故障期间泄漏的 FA
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-17 DOI: 10.1007/s10512-024-01102-x
A. B. Tereshchenko, E. I. Golubev
{"title":"Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection","authors":"A. B. Tereshchenko,&nbsp;E. I. Golubev","doi":"10.1007/s10512-024-01102-x","DOIUrl":"10.1007/s10512-024-01102-x","url":null,"abstract":"<div><p>The paper considers the processes involved in leaking fuel elements during the shutdown and preparation of a reactor for refueling in the case of a defect located at the bottom, in the middle, or at the top of the fuel column. The volume and activity of gaseous fission products released during fuel cladding failure detection were evaluated using the mast sipping system of the refueling machine. It is demonstrated that the sensitivity of the beta-radiometer, which starts at 37 kBq/m<sup>3</sup>, provides for the detection of leaking fuel elements at any power density located at various locations of the defect along its height. Neglecting to wash all fuel elements in the FA with bubble air may result in a failure to detect leaking fuel elements.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"206 - 210"},"PeriodicalIF":0.4,"publicationDate":"2024-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141739038","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
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties 减慢快堆动力学速度以增强其自我保护性能的方法
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2024-07-15 DOI: 10.1007/s10512-024-01091-x
Yu. A. Dolgov, A. V. Lopatkin, V. N. Leonov, I. B. Lukasevich, I. S. Slesarev
{"title":"Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties","authors":"Yu. A. Dolgov,&nbsp;A. V. Lopatkin,&nbsp;V. N. Leonov,&nbsp;I. B. Lukasevich,&nbsp;I. S. Slesarev","doi":"10.1007/s10512-024-01091-x","DOIUrl":"10.1007/s10512-024-01091-x","url":null,"abstract":"<div><p>The concept of slowing down the kinetics of a fast reactor, according to which a rapid reactivity insertion is used to reduce the development rate of transients at initial events, is aimed at achieving a higher level of reactor self-protection. The paper presents a set of studies on the engineering and technical implementation of this concept on the example of a high-power fast lead-cooled reactor. Considering a hypothetical initial event with a rapid insertion of a complete reactivity margin, the stability of the reactor with the slowed down kinetics in relation to such an event was analyzed. An updated physical-mathematical apparatus is proposed for evaluating the slowed-down kinetics and calculating the dynamics of transient processes. The basic principles for the formation of a reflector for such a reactor based on formulated criteria for slowing down the kinetics include the use of <sup>208</sup>Pb and weakly neutron-absorbing materials, as well as the optimum location of various structural elements in the reflector. The theoretical possibility of achieving a slowed-down kinetics in layouts that meet the developed principles is demonstrated.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 3-4","pages":"121 - 127"},"PeriodicalIF":0.4,"publicationDate":"2024-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141645202","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
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
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