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Optimization of spent nuclear fuel reprocessing for reducing radioactive waste
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-21 DOI: 10.1007/s10512-025-01173-4
Yu. A. Evsyukova, O. V. Shmidt, A. A. Rykunova, V. A. Kaschcheev, A. Yu. Shadrin
{"title":"Optimization of spent nuclear fuel reprocessing for reducing radioactive waste","authors":"Yu. A. Evsyukova,&nbsp;O. V. Shmidt,&nbsp;A. A. Rykunova,&nbsp;V. A. Kaschcheev,&nbsp;A. Yu. Shadrin","doi":"10.1007/s10512-025-01173-4","DOIUrl":"10.1007/s10512-025-01173-4","url":null,"abstract":"<div><p>When selecting processes for modernizing existing or newly created radiochemical plants, technologists and developers face many challenges, including issues of economic efficiency. Mathematical simulation represents the best way to optimize process solutions using various criteria. As a tool for solving such problems, we propose to use the VIZART software package implementing the end-to-end optimization calculation of closed nuclear fuel cycle processes, including the optimal ratio for radioactive waste of different activity levels. Using this module, we have analyzed the main components of costs for post-reactor handling of spent nuclear fuel. The minimum cost of handling high-level radioactive waste was calculated for several scenarios of a closed nuclear fuel cycle. The conducted comparative analysis of radioactive waste conditioning technologies considered various types of spent nuclear fuel reprocessing in the modules of pilot demonstration and industrial energy complexes.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"24 - 30"},"PeriodicalIF":0.4,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143622003","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
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-19 DOI: 10.1007/s10512-025-01181-4
V. D. Sizarev, A. V. Smirnov, A. G. Sokolova, F. Ya. Balitsky
{"title":"Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor","authors":"V. D. Sizarev,&nbsp;A. V. Smirnov,&nbsp;A. G. Sokolova,&nbsp;F. Ya. Balitsky","doi":"10.1007/s10512-025-01181-4","DOIUrl":"10.1007/s10512-025-01181-4","url":null,"abstract":"<div><p>The paper considers the issue of ensuring the reliability and nuclear safety of unique rotary equipment represented with the mobile neutron reflector of the IBR-2M research reactor. The specifics of its operation under the conditions of inaccessibility for visual control and maintenance dictates the need to use indirect methods of monitoring and diagnostics. The performed study demonstrates the efficiency of combined vibration monitoring and diagnostics for detecting operational defects of the PO-3 mobile reflector. Both conventional spectral and non-standard probabilistic methods of vibration analysis are used, including the <i>S-</i>discriminant analysis adapted to the reference state of equipment. The gamma-spectral analysis of radioactive impurities in the reflector lubricant oil significantly increases the reliability of recognizing the technical state of complex machinery. The example of the PO-2R mobile reflector demonstrates the applicability of the neutron activation method to identify the release of metal microparticles in the oil lubricant due to the degradation processes of exhausted equipment.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"87 - 93"},"PeriodicalIF":0.4,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143621812","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
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-11 DOI: 10.1007/s10512-025-01179-y
E. V. Bogdanova, V. A. Bolnov, S. S. Grigoriev, A. S. Emelina, S. A. Malkin, A. S. Ushatikov
{"title":"Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant","authors":"E. V. Bogdanova,&nbsp;V. A. Bolnov,&nbsp;S. S. Grigoriev,&nbsp;A. S. Emelina,&nbsp;S. A. Malkin,&nbsp;A. S. Ushatikov","doi":"10.1007/s10512-025-01179-y","DOIUrl":"10.1007/s10512-025-01179-y","url":null,"abstract":"<div><p>The present paper considers the RASNAR-GAZ validation of the computational model for the steam generator. The model is designed to calculate non-stationary modes of gas-cooled nuclear power plants. For this purpose, experimental data of the THTR-300 reactor were used. The performed validation proved the RASNAR-GAZ software to describe the main parameters of heat and mass transfer between helium and water in a steam generator with accuracy sufficient for engineering calculations of both static and dynamic modes.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"71 - 77"},"PeriodicalIF":0.4,"publicationDate":"2025-02-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143622187","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
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-11 DOI: 10.1007/s10512-025-01175-2
A. V. Rodin, A. M. Koshcheeva, M. V. Skvortsov, A. V. Ponizov, A. S. Nikulin
{"title":"Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity","authors":"A. V. Rodin,&nbsp;A. M. Koshcheeva,&nbsp;M. V. Skvortsov,&nbsp;A. V. Ponizov,&nbsp;A. S. Nikulin","doi":"10.1007/s10512-025-01175-2","DOIUrl":"10.1007/s10512-025-01175-2","url":null,"abstract":"<div><p>The paper describes experimental studies assessing the release of radionuclides into the gas phase from aqueous process media. These include simulators of solutions after clarification and dissolution of spent nuclear fuel (SNF) and re-extraction of transplutonium and rare earth elements. We propose algorithms for calculating the release of elements and its rate during the transition to the gas phase from simulant solutions. The dependence of the radionuclide release rate on the temperature, air flow, and composition of the process medium is shown. In terms of specific activity, strontium, cesium, cerium, ruthenium, europium, and technetium make the greatest contribution to the activity of the gas phase.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"38 - 46"},"PeriodicalIF":0.4,"publicationDate":"2025-02-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143622188","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
Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-10 DOI: 10.1007/s10512-025-01176-1
V. A. Grachev, A. B. Sazonov, O. S. Bystrova
{"title":"Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit","authors":"V. A. Grachev,&nbsp;A. B. Sazonov,&nbsp;O. S. Bystrova","doi":"10.1007/s10512-025-01176-1","DOIUrl":"10.1007/s10512-025-01176-1","url":null,"abstract":"<div><p>The present paper considers the simulated distribution of tritium in the primary circuit of an NPP with a VVER reactor and its auxiliary systems. The activity of tritium in the coolant and auxiliary reactor systems varies during power operation, passing through a maximum. The results of calculations for different flow rates of uncontrolled leakage and drain waters are compared with experimental data on tritium activity in the systems of operating VVER NPPs. Calculation results satisfactorily agree with more than 300 points of experimental data, given the value spread of approximately two orders of magnitude. The study assesses the tritium activity of the spray pond and compare calculated tritium emissions with measurement results. As in the case of the primary circuit, calculations are satisfactorily consistent with experimental data. Thus, the calculation method predicts reliable values of tritium activity in liquid media of VVER reactor units.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"47 - 54"},"PeriodicalIF":0.4,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143622185","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
Regulatory aspects and practice of radioactive waste management in the Republic of Kazakhstan
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-10 DOI: 10.1007/s10512-025-01185-0
I. L. Tazhibayeva, A. Kh. Klepikov, O. G. Romanenko, A. P. Blynskiy
{"title":"Regulatory aspects and practice of radioactive waste management in the Republic of Kazakhstan","authors":"I. L. Tazhibayeva,&nbsp;A. Kh. Klepikov,&nbsp;O. G. Romanenko,&nbsp;A. P. Blynskiy","doi":"10.1007/s10512-025-01185-0","DOIUrl":"10.1007/s10512-025-01185-0","url":null,"abstract":"<div><p>The article discusses issues of state safety regulation, as well as policy and practice of handling accumulated and generated radioactive waste in the Republic of Kazakhstan. Approaches to waste classification from the perspective of economic factors are described. The best practices and general approaches used in various countries to search for long-term and reliable solutions of radioactive waste management are considered.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 1-2","pages":"121 - 128"},"PeriodicalIF":0.4,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143622184","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
Experimental justification of a pyrochemical technology for reprocessing of mixed uranium-plutonium nitride spent nuclear fuel
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-10 DOI: 10.1007/s10512-024-01164-x
Yu. P. Zaikov, A. E. Galashev, A. S. Kholkina, V. A. Kovrov, Yu. S. Mochalov
{"title":"Experimental justification of a pyrochemical technology for reprocessing of mixed uranium-plutonium nitride spent nuclear fuel","authors":"Yu. P. Zaikov,&nbsp;A. E. Galashev,&nbsp;A. S. Kholkina,&nbsp;V. A. Kovrov,&nbsp;Yu. S. Mochalov","doi":"10.1007/s10512-024-01164-x","DOIUrl":"10.1007/s10512-024-01164-x","url":null,"abstract":"<div><p>The article describes pyrochemical processing of spent nuclear fuel, including high-temperature processing, electrochemical reduction of actinide oxides to metals in a chloride-oxide melt, anode manufacture by induction remelting, and electrolytic refining of actinides in a chloride melt. The technology has been proven and tested on model nuclear fuel. The obtained data underlay the requirements for reagents and support systems. Moreover, these data were used for the design of equipment and pyrochemical section of the processing module at the pilot demonstration energy complex as part of the power unit with the BREST-OD-300 lead-cooled reactor currently being constructed at the site of the Siberian Chemical Combine JSC, Russian Federation.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 5-6","pages":"300 - 306"},"PeriodicalIF":0.4,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143571022","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
Fast reactors in the strategic nuclear power development scenarios of the Russian Federation
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-02-04 DOI: 10.1007/s10512-024-01154-z
E. O. Adamov, A. A. Kashirsky
{"title":"Fast reactors in the strategic nuclear power development scenarios of the Russian Federation","authors":"E. O. Adamov,&nbsp;A. A. Kashirsky","doi":"10.1007/s10512-024-01154-z","DOIUrl":"10.1007/s10512-024-01154-z","url":null,"abstract":"<div><p>The leading design organizations of the Russian nuclear industry develop nuclear power facilities to satisfy almost any segment of the energy market. Within the framework of the Proryv project direction, a new technological platform for nuclear power is being created based on nuclear power plants with high-capacity reactors and a closed nuclear fuel cycle. Demand for fast reactors in the Russian Federation was thoroughly justified in the 2018 Strategy for the Development of Nuclear Power in the Russian Federation until 2050 and Prospects for the Period until 2100, as well as its updated 2022 version. It should be noted that the role of fast reactors in the energy system may vary depending on the goals and objectives set in terms of the fuel supply and adopted approach to spent fuel and waste management. The article examines various prerequisites that influence the parameters of fast reactors, taking into account these factors in the context of strategic planning along with the latest computational and analytical studies.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 5-6","pages":"215 - 221"},"PeriodicalIF":0.4,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143570930","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
Technetium in a closed nuclear fuel cycle with transmutation
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-01-29 DOI: 10.1007/s10512-024-01162-z
A. Yu. Vakhrushin, A. A. Zherebtsov
{"title":"Technetium in a closed nuclear fuel cycle with transmutation","authors":"A. Yu. Vakhrushin,&nbsp;A. A. Zherebtsov","doi":"10.1007/s10512-024-01162-z","DOIUrl":"10.1007/s10512-024-01162-z","url":null,"abstract":"<div><p>The article considers the behavior of technetium during water-extraction reprocessing of spent nuclear fuel using the technological scheme applied at the RT‑1 plant of the Mayak Production Association, Russian Federation. The raffinate of the plutonium refining cycle concentrates 98.5% of technetium for subsequent selective precipitation with large amine cations. These compounds are calcined to obtain metal technetium or its carbide, which can be used as targets for technetium transmutation. In addition, this article provides options of technetium transmutation and target reprocessing for producing stable ruthenium isotopes.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 5-6","pages":"288 - 293"},"PeriodicalIF":0.4,"publicationDate":"2025-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143571173","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
Evolution of fast reactors. The role of a BN-350 reactor
IF 0.4 4区 工程技术
Atomic Energy Pub Date : 2025-01-29 DOI: 10.1007/s10512-024-01155-y
V. M. Troyanov, A. A. Kamaev
{"title":"Evolution of fast reactors. The role of a BN-350 reactor","authors":"V. M. Troyanov,&nbsp;A. A. Kamaev","doi":"10.1007/s10512-024-01155-y","DOIUrl":"10.1007/s10512-024-01155-y","url":null,"abstract":"<div><p>The history of the development and operation of BN-350 reactors is analyzed from the position of solving the problems that arose at the stage of the industrial operation of sodium-cooled fast reactors. The main tasks faced the BN-350 project are formulated. The stages of the design, construction, commissioning, and operation of an industrial BN-350 reactor is chronologically reviewed, including a description of the encountered problems and achieved results. The effect of the knowledge obtained during the development and operation of BN-350 reactors on the selection of technical solutions for the reactor, main equipment, and parameters of sodium circuits implemented in BN-600 and BN-800 projects is demonstrated.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 5-6","pages":"222 - 232"},"PeriodicalIF":0.4,"publicationDate":"2025-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143571182","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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