Pub Date : 2024-07-02DOI: 10.1007/s10512-024-01093-9
E. V. Rodionova, A. L. Balanin, A. V. Grol, V. A. Nevinitsa, P. A. Fomichenko
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.
{"title":"The role and position of HTGR reactor technology in the development of the Russian energy","authors":"E. V. Rodionova, A. L. Balanin, A. V. Grol, V. A. Nevinitsa, P. A. Fomichenko","doi":"10.1007/s10512-024-01093-9","DOIUrl":"https://doi.org/10.1007/s10512-024-01093-9","url":null,"abstract":"<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>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-20DOI: 10.1007/s10512-024-01086-8
E. A. Shiverskiy, A. N. Terekhin, S. S. Andreev, A. S. Nikulin
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.
{"title":"Formation of design and operational databases on the reliability of equipment at Nuclear Fuel Cycle facilities","authors":"E. A. Shiverskiy, A. N. Terekhin, S. S. Andreev, A. S. Nikulin","doi":"10.1007/s10512-024-01086-8","DOIUrl":"https://doi.org/10.1007/s10512-024-01086-8","url":null,"abstract":"<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>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-20DOI: 10.1007/s10512-024-01089-5
A. B. Tereshchenko, E. I. Golubev
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.
{"title":"Increased sensitivity of fuel cladding failure detection","authors":"A. B. Tereshchenko, E. I. Golubev","doi":"10.1007/s10512-024-01089-5","DOIUrl":"https://doi.org/10.1007/s10512-024-01089-5","url":null,"abstract":"<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>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01081-z
A. Smirnov, G. Sulaberidze
{"title":"Debatable issues on the derivation of the separation potential for multicomponent mixtures","authors":"A. Smirnov, G. Sulaberidze","doi":"10.1007/s10512-024-01081-z","DOIUrl":"https://doi.org/10.1007/s10512-024-01081-z","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01080-0
V. Palkin
{"title":"Determination of separation power for the separation of a multicomponent isotope mixture","authors":"V. Palkin","doi":"10.1007/s10512-024-01080-0","DOIUrl":"https://doi.org/10.1007/s10512-024-01080-0","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01075-x
Yu. V. Alimov, A. V. Kaplienko, P. B. Kuznetsov, I. 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, A. V. Kaplienko, P. B. Kuznetsov, I. Rozhdestvenskiy, A. V. Slobodchikov, V. K. Davydov, A. P. Zhirnov, S. S. Lebedev","doi":"10.1007/s10512-024-01075-x","DOIUrl":"https://doi.org/10.1007/s10512-024-01075-x","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01076-w
V. A. Adarchenko, S. A. Andreev, S. S. Besov, A. Vaivod, D. Khmelnitsky, A. A. Yudov
{"title":"Integral experiments with a cylindrical multiplying system of metal plutonium","authors":"V. A. Adarchenko, S. A. Andreev, S. S. Besov, A. Vaivod, D. Khmelnitsky, A. A. Yudov","doi":"10.1007/s10512-024-01076-w","DOIUrl":"https://doi.org/10.1007/s10512-024-01076-w","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01078-8
I. V. Kuzmin, A. 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, A. Leshchenko, A. V. Nosov, V. P. Smirnov, R. N. Shamsutdinov, Y. S. Mochalov, L. P. Sukhanov","doi":"10.1007/s10512-024-01078-8","DOIUrl":"https://doi.org/10.1007/s10512-024-01078-8","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01074-y
D. A. Klinov, M. Y. Semenov, G. M. Mikhailov, A. Peregudov, V. A. Mishin, N. V. Solomonova, A. N. Kryukov, M. R. Farakshin, S. B. Belov, A. E. Kuznetsov, V. N. Ignatiev, G. Y. Dubova
{"title":"Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading","authors":"D. A. Klinov, M. Y. Semenov, G. M. Mikhailov, A. Peregudov, V. A. Mishin, N. V. Solomonova, A. N. Kryukov, M. R. Farakshin, S. B. Belov, A. E. Kuznetsov, V. N. Ignatiev, G. Y. Dubova","doi":"10.1007/s10512-024-01074-y","DOIUrl":"https://doi.org/10.1007/s10512-024-01074-y","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141363839","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}
Pub Date : 2024-06-10DOI: 10.1007/s10512-024-01088-6
E. V. Semenov, V. V. Kharitonov
{"title":"Influence of the composition and burnup of accident-tolerant fuel on the fuel component of NPP electricity cost","authors":"E. V. Semenov, V. V. Kharitonov","doi":"10.1007/s10512-024-01088-6","DOIUrl":"https://doi.org/10.1007/s10512-024-01088-6","url":null,"abstract":"","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141364756","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}
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