Global Nuclear Safety最新文献

{"title":"Safety culture development at an industrial enterprise (on the example of «Atommash» Branch of «AEM-Technologies» JSC in Volgodonsk)","authors":"T. S. Popova, V. Rudenko, A. A. Popov, V. A. Bondarenko, Y. Evdoshkina","doi":"10.26583/gns-2023-04-08","DOIUrl":"https://doi.org/10.26583/gns-2023-04-08","url":null,"abstract":"The article chooses Atommash Branch of AEM-Technologies JSC in Volgodonsk as the object of study, which is a supplier of integrated solutions including engineering, design, manufacturing, supply, installation and service of power equipment for nuclear power facilities, thermal power plants, as well as for enterprises of the gas and petrochemical industries. The subject area chosen is safety culture (SC), which the enterprise implements in order to fulfil the strategy of ROSATOM to achieve technological leadership and sovereignty on a global scale. The purpose of the study is to identify the main characteristics of this phenomenon based on the analysis of existing theories and practices of safety culture management and to correlate them with the specifics of the process of implementing the safety culture at the Atommash the branch of JSC AEM-Technologies in Volgodonsk. The theoretical analysis of scientific literature on the research problem, graphical method, statistical data analysis, retrospective analysis and study of local acts of the research object in terms of safety culture provision are the main methods used in writing the paper. The main result of the research is the conclusion that safety culture of the branch as well as its organisational culture, refers to collective values and beliefs. Formation and maintenance of high level of safety culture is achieved by prioritising safety over economic and production goals, ensuring that each employee understands the impact of their activities on safety and the consequences that may result from non-compliance or poor performance of safety culture requirements;#, ensuring that each manager and employee understands the inadmissibility of concealing errors in their activities, the need to identify and eliminate the causes of their occurrence, the need for continuous self-improvement, изучения и внедрения передового опыта.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"23 11","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139167394","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Analysis and optimization of energy release and fuel burnup nonuniformity in the WWER-1000 fuel assembly","authors":"A. Lapkis, A. S. Starchenko, D. V. Trishechkin, I. Y. Popova","doi":"10.26583/gns-2023-04-07","DOIUrl":"https://doi.org/10.26583/gns-2023-04-07","url":null,"abstract":"The paper considers and systematises the options of fuel assemblies (FAs) for the WWER-1000 reactor. In the Serpent neutron-physics code, an infinite-height fuel assembly with six fuel pins is modelled using the U49G6 pattern used in the WWER-1000 «large series» fuel assemblies. Variants of fuel elements placement with lower non-uniformity of energy release on fuel assemblies were selected as a result of calculations, and the influence of the number of fuel elements and their placement on reactivity was evaluated.  It is shown that gadolinium fuel elements placement in the fourth ring is optimal from the point of view of non-uniformity of fuel energy release and burn-up depth. The influence of the fuel assembly layout on the fuel burnup depth for separate groups of fuel pins is considered. The variant of reduction of computational resources expenditures by means of allocation of the most different in energy release and burnup groups of gadolinium fuel rods is offered. Comparison of the investigated assemblies with the existing U49G6 type fuel assembly is carried out. A method to estimate the underproduction of thermal energy in the fuel assembly associated with the non-uniformity of fuel element burnup in it, while maintaining the maximum burnup depth for individual fuel elements at the level of existing samples is proposed. On the basis of the analysis of the value of underproduction, a variant of improving the configuration of fuel assemblies with six fuel elements is proposed to equalise the field of energy release and reduce unproductive fuel losses. Therefore, enrichment in the first, second and tenth rings of fuel elements, counting from the centre tube of the fuel assembly, can be reduced. As a result of such profiling, the burnup depth of the most burned-out fuel elements in the cassette can be reduced to 1.015 of the average for the fuel assembly.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"64 22","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139167515","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Estimation of the effective length of microcracks occurring in the water-steam pipeline at cyclic operation mode of NPP steam generator","authors":"A. Elokhin","doi":"10.26583/gns-2023-04-05","DOIUrl":"https://doi.org/10.26583/gns-2023-04-05","url":null,"abstract":"During operation of water-water reactors including KLT-40 type reactors widely used nowadays on icebreakers and floating power units (FPU), the issue of the duration of safe operation of steam generators is acute. The problem is connected with the formation of microcracks in the steam generator water and steam piping during normal operation at power, through which radioactive nitrogen 16N7 enters the steam piping, the content of which in the steam is just a sign of leakage failure of the steam generator second circuit water and steam piping. This effect, further named \"leaks\", was considered earlier in a number of works of the authors under conditions of cyclic operation of the steam generator water-steam mode. In the present work the main attention is paid to mathematical and physical analysis of the mechanisms causing the formation of microcracks in the steam pipeline of a steam generator arising in the steam pipeline region in which water and steam pressures are balanced, and their effective length is estimated. Calculations of temperature distribution along the steam-pipe thickness in the steam-water transition region at periodic \"slamming\" of this region with water are carried out. It is shown that depending on the time period of steam-water oscillations, the radial temperature distribution along the tube thickness shows a significant difference in the distribution at a constant temperature on the outer surface of the tube, and the maximum temperature difference is observed in the area of the inner surface of the tube. The distribution of mechanical stresses arising in the tube metal is characterized by a linear dependence of stresses on temperature, the maximum value of which corresponds to the maximum temperature difference characteristic of the area of the inner surface of the tube. This allows us to state that the formation of cracks starts exactly from the area of the inner surface of the tube of the steam generator in the specified transitional area of the tube.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"45 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166585","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Evaluation of measuring magnetic anisotropy parameters method to monitor the development of erosion and corrosion wear of equipment","authors":"A. K. Adamenkov, I. Veselova","doi":"10.26583/gns-2023-04-06","DOIUrl":"https://doi.org/10.26583/gns-2023-04-06","url":null,"abstract":"The paper presents the results of further research in the field of assessing the development of erosion and corrosion wear (ECW) of pipeline elements using a magnetic and anisotropic method to monitor the stress-strain state of ferromagnetic material. The conducted studies show that the recorded parameters of the magnetic anisotropic method, such as the principal mechanical stress difference, make it possible to unambiguously establish a quantitative correspondence to the level of stresses operating in the controlled zone. The possibility of determining the correspondence of the level of effective stresses to the value of the principal mechanical stress difference recorded by the StressVision scanner during the inspection of the structure is proven. The paper shows that in order to organize monitoring of the development of ECW using the magnetic anisotropic method it is necessary to monitor periodically changes in the principal mechanical stress difference and its dispersion and when fixing cut-off points, prescribe additional examinations with other more labor-intensive methods. The possibility of organizing monitoring of ECW equipment development based on the use of a pipeline resource forecasting mechanism in accordance with the provisions of regulatory documentation is confirmed.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"36 6","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166794","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comparative experiment on the efficiency of water cooling in photovoltaic modules in the climatic conditions of Southern Russia","authors":"V. Ilyichev, L. K. Zaynutdinova, E. I. Terukov, M. Y. Mikhailov","doi":"10.26583/gns-2023-04-02","DOIUrl":"https://doi.org/10.26583/gns-2023-04-02","url":null,"abstract":"The problems of ensuring the safety of operation of nuclear power plants are always paid increased attention. In addition to the self-contained diesel generator sets used to maintain the operation of safety systems in case of loss of external power supply, it is also advisable to consider the use of more environmentally friendly self-contained photovoltaic units at this stage. The work is aimed at a comparative experimental study of the efficiency of water cooling in real natural climatic conditions of Southern Russia. In this experiment, cooled and uncooled photovoltaic modules are simultaneously exposed to a complex of variable weather factors: solar radiation, cloudiness, wind, pressure, temperature and humidity of the environment. Both modules have loads connected via MPPT controllers. The effect of water cooling on the energy efficiency of photovoltaic modules assembled from silicon heterojunction technology (HJT) solar cells was studied. The solar panels were made from 130 micron thick HJT cells interconnected using SmartWire contact technology. It reduces power loss due to possible defects such as cracks. The conditions for ensuring the highest degree of similarity between the parameters of the cooled and uncooled modules have been met. A comparative experimental study was conducted in Astrakhan State University using a long-term monitoring system for the characteristics of photovoltaic modules. This is a test photovoltaic system (TPS), built on the basis of the Paragraph PL2 electronic recorder. A significant increase in module output when working with cooling was established. At insolation of 987.5 W/m2, the power generated by the cooled module was 93.0297 W, while the power of the module without cooling was 79.306 W. The difference comprised 13.7237 watts. Power increased by 17%. In the experiment, the average efficiency value when the module was cooled was 0.15977. When uncooled, it was 0.13764. The efficiency intensified by 2.21%. This increase is significant. The results obtained confirm the fairly high efficiency of water cooling in photovoltaic modules in real natural operating conditions for regions with high ambient temperatures, Southern Russia, in particular","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"53 8","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Operational determination of current-voltage characteristics welding power sources in nuclear engineering","authors":"V. A. Vinniychuk, N. N. Podrezov, Yu.V. Doronin","doi":"10.26583/gns-2023-04-03","DOIUrl":"https://doi.org/10.26583/gns-2023-04-03","url":null,"abstract":"Welding equipment is everywhere equipped with modern digital welding arc power systems based on microprocessor and other logical element bases. At the same time, there is a tendency to minimize information not only for Chinese, but also for equipment of well-known brands, so it is important to quickly monitor the accuracy of the accompanying documentation in order to avoid deterioration in the quality of products and waste of time re-equipment. Modern recorders of welding processes allow several times to reduce the time for checking the declared characteristics of all power sources certified for use in the nuclear power industry. Among the characteristics and service functions analyzed by the recorder, it should be noted static current-voltage characteristics, oscillograms of «hot start», «afterburner» and «anti-sticking». The paper presents the data of selective tests for compliance with the declared passport data of inverter power supplies INEM-200T (MMA process), Artsen CM-500 (MAG process) and ION 48-900 (SAW process). Based on the results of the research, conclusions were drawn about the benefits of using the proposed model of the welding process recorder at enterprises of heavy nuclear engineering.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"39 16","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166577","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Resource-saving management paradigm in projects of Rosatom State Corporation machine-building division enterprises","authors":"M. V. Golovko, A. M. Potyavin, I. A. Ukhalina, A. Antsibor, N. A. Efimenko, Z. S. Rogacheva","doi":"10.26583/gns-2023-04-09","DOIUrl":"https://doi.org/10.26583/gns-2023-04-09","url":null,"abstract":"The article analyzes current problems and successful practices of implementing lean technologies at Russian enterprises. The purpose of the presented research work is to develop relevant mechanisms, search for tools and technologies with the help of which the mentioned problems (general and specific) can be overcome. The novelty of the research lies in the justification of the transition to a new paradigm of resource-saving management and adaptation of project management and business analysis tools to the projects of lean technology implementation. To investigate the trends in the formation of a new management paradigm based on the active involvement of resource-saving tools, such general scientific methods as analysis of scientific and specialized literature, synthesis, logical and analytical methods were used. Materials of internal reporting of the enterprises of the machine-building division of Rosatom State Corporation are used in the work. The main problems of implementing lean technologies at Russian enterprises are formulated and ranked. The list of enterprise management techniques in accordance with the new management paradigm is presented, as well as their capabilities to improve the efficiency of management decisions. The importance of digital technologies for ensuring the effectiveness of resource-saving projects is substantiated. An approximate strategic map for nuclear power engineering enterprises, based on the balanced scorecard methodology, in the implementation of lean decisions is developed. The most effective projects of enterprises of the machine-building division of the State Atomic Energy Corporation ROSATOM were identified, which can become benchmarking objects for scaling experience among enterprises of other divisions of the State Corporation, as well as for enterprises of other industries and spheres of activity. Despite the rather high degree of development of the problem of lean technology implementation, new realities form specific factors that can make the previous scientific and practical results irrelevant. Further research of this topic should be carried out on the basis of analyzing the dynamics of the external environment leading to fluctuations in the industry and regional markets.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"11 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166697","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Justification of obtaining fine-grained structure of welded joints at high-intensity impulse effect on welding circuit","authors":"S. M. Burdakov, V. Ratushny, Yu. V. Zayarov","doi":"10.26583/gns-2023-04-04","DOIUrl":"https://doi.org/10.26583/gns-2023-04-04","url":null,"abstract":"An effective method of improving the reliability of operation of thermal and nuclear power facilities is to improve the quality of manufacture, installation and repair of their thermal and generating power equipment. One of the ways to improve the quality, technological and service properties of welded joints in the process of their implementation is to influence the structure of the crystallizing metal by thermal, electric high-intensity impulse effect for its grinding. This work proposes the results of an experimental study to substantiate the production of a fine-grained structure of welded joints obtained using manual arc welding with coated electrodes at a high-intensity impulse effect (QPS) with a fi.g.= 40×103 Gts frequency, voltage Ui.g.= 80.0 V, on the welding circuit. The energy characteristics of the process can be used to assess the effect of high-intensity impulse action on the welding circuit, including the arc plasma and the structure of the resulting weld. As the energy characteristics of the welding process, the welding current Iwd, the voltage on the arc discharge Ud, the power Rp. Oscillograms of the specified characteristics were obtained, as well as the values of the maximum (peak) and average power released in the welding circuit when QPS is exposed to it and without its use were determined. Energy evaluation of input of additional high-intensity pulse effect on welding circuit as ultrasonic energy for cavitations of surface layer of welding bath at QPS was performed. Direct current arc discharge at application of high-intensity pulse effect with frequency of fi.g.= 40×103Gts (QPS) is source of cavitations of liquid phase of metal of welding bath in limited surface layer of preset thickness. It can be assumed that the crystallization of the bath takes place in layers when the welding circuit is subjected to high-intensity pulse exposure with a frequency of fi.g.= 40×103 Gts (QPS). In this case, the growing crystals break when the liquid phase oscillates due to friction forces arising between the moving liquid phase and the growing crystal. At the site of crystal fracture, zones of dynamically super cooled metal are formed, which leads to the appearance of new crystallization centers, and a fine-grained structure of the weld appears.","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"27 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166601","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Salting out of americium-241 in the sorption process using a solid-phase extractant based on TODGA","authors":"A. A. Savelev, V. I. Rachkov","doi":"10.26583/gns-2023-04-01","DOIUrl":"https://doi.org/10.26583/gns-2023-04-01","url":null,"abstract":"Today, the «Proryv» project is developing effective methods of reprocessing irradiated nuclear fuel (SNF) to return long-lived radionuclides to the fuel cycle to close it. One of the challenges of closed fuel cycle development is the reprocessing of highly active nitric acid raffinates from the PUREX-process. To achieve this task, it is necessary to separate americium-241 from liquid radioactive waste. When processing and fractionating liquid radioactive waste, extraction and sorption technologies for the extraction, purification and concentration of radionuclides are widely used. The highest efficiency and selectivity in the extraction processes of actinoids (III) and lanthanides (III) with rare earth elements (REE) and transplutonium elements (TPE) from nitric acid solutions of spent nuclear materials reprocessing were shown by extractants based on N, N, N', N'-tetraoctyldiglycolamide (TODGA). Before using a solid-phase extractant based on TOGDA, the ions of the substance in solution must be converted to neutral complexes or other non-dissociated compounds. This can be achieved by adding neutral salts to the solution, which reduce the solubility of the elements to be separated, shift the extraction distribution and significantly increase the extraction efficiency. The extracted substance is extracted in the form of a new phase - solid precipitate, liquid or gas phase, and in the case of liquid extraction there is an increase in the capacity of the extractant for the target component. Therefore, the addition of salts-salting agents to the aqueous phase to increase the ionic strength of the solution increases the distribution coefficients of extracted substances, which in turn increases the capacity of sorbents. The purpose of this work is to study the process of salting out of americium-241 during sorption using an experimental modified sample of solid-phase extractant based on TODGA in the studied model solutions of liquid radioactive waste with a uranium macrocomponent for different NaNO3 contents. The study revealed that the highest distribution coefficients for the sorption of americium-241 and uranium were obtained in a solution containing 100 g/l NaNO3, but for uranium this effect is much less pronounced than for americium-241. During the study of the sorption kinetics of americium-241 and uranium, the salting effect was revealed, which is confirmed by the values of the equilibrium concentrations of americium-241 and uranium in solution at the same time point but with different NaNO3 concentrations. The difference in the equilibrium concentrations for americium-241 was an order of magnitude towards its decrease when NaNO3 concentration was increased up to 100 g/litre. The use of this effect makes it possible to obtain the maximum capacity for americium-241 in the system with uranium macrocomponents","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"38 15","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139166764","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Application of risk-based approach in switching operations preparation at Novovoronezh NPP","authors":"A. Mozgovoj, I. S. Rukin, A. Lebedeva","doi":"10.26583/gns-2023-02-10","DOIUrl":"https://doi.org/10.26583/gns-2023-02-10","url":null,"abstract":"The article discusses one of the problematic issues of operating nuclear power plants - revenue losses caused by staff mistakes. Existing methods and approaches to reducing the number of such incidents are analyzed. Despite the efforts made, the problem remains relevant. One of the directions for reducing the number of equipment failures is the study and use of internal and external operational experience. A description is given of a system for preventing the recurrence of negative operating experience, developed at the Novovoronezh Nuclear Power Plant, which is used in preparation for switching equipment. The system is an information base, the information in which is structured by types of equipment used at the Novovoronezh Nuclear Power Plant, allowing only the information directly related to the upcoming switches to be communicated to the operational staff. Suggestions for its further improvement, taking into account the recommendations of the International Atomic Energy Agency, are considered. A forecast is given for the dynamics of reducing the number of violations after the introduction of this system into industrial operation.​","PeriodicalId":113403,"journal":{"name":"Global Nuclear Safety","volume":"1005 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116239835","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}