Nuclear Engineering Research Articles

For a bright future. Cuban nuclear engineers studying in late socialist Hungary

PurposeThis research aims to contribute to History of Education Studies as well as to New Cold War Studies, by examining a Reactor Technology Specialist Engineer program, launched in Hungary three times in the 1980s for Cuban nuclear engineers, graduates of the University of Havana.Design/methodology/approachThe institutional setting, the content of the program, the teaching staff, the students, and the outcomes are studied. The factors that motivated the birth of this special program are examined, including the following areas; in what ways it was different from the courses in which foreign students participated in Hungary; what its strengths and weaknesses were; how we can learn from this past experience and what relevance it has for the present.FindingsThe analysis – carried out within the context of Cuban–Hungarian relations in the Cold War – demonstrates that these two satellite countries used the fields of science and education to widen their international possibilities and at the same time to reinforce their national interests by cooperating with each other.Originality/valueThe investigation is based on archival sources, university yearbooks and journals as well as contemporary Hungarian press. Written sources were complemented by interviews with Cuban students and Hungarian teaching staff, thus providing a personal perspective, balancing official views.

GDSA framework, a computational framework for complex modeling problems in radioactive waste management

This paper details a computational framework to produce automated, graphical workflows, and how this framework can be deployed to support complex modeling problems like those in nuclear engineering. Key benefits of the framework include: automating previously manual workflows; intuitive construction and communication of workflows through a graphical interface; and automated file transfer and handling for workflows deployed across heterogeneous computing resources. This paper demonstrates the framework's application to probabilistic post-closure performance assessment of systems for deep geologic disposal of nuclear waste. However, the framework is a general capability that can help users running a variety of computational studies.

In situ XAFS-XRD study of the Zr-Y2O3 interaction at extra-high temperatures.

The in situ measurement technique for a metal/metal-oxide mixture at extra-high temperature above 2000 K has been desired in the field of nuclear safety engineering. In the present study, we succeeded in simultaneous XAFS-XRD measurements of the Zr oxidation [Zr + O → Zr(O) + ZrO2] up to 1952 K and ZrO2-Y2O3 reaction from 1952 to 2519 K. The chemical shift during Zr oxidation was observed in the absorption spectra around the Zr K-edge, and the interatomic cation-cation and cation-oxygen distances obtained by the fitting analysis of EXAFS during the Y2O3-ZrO2 reaction are explained. Also, the temperature dependency of the anharmonic effect was investigated by comparing the fitted second- and third-order cumulants with the theoretical ones in which the Morse potential was applied as an interatomic potential, giving a good explanation about the local structure dynamics. Finally, the applicability of the developed system to investigation of nuclear fuel materials, such as UO2-Zr, is discussed.

A journey from nuclear engineer to higher education: A conversation with Pingchien Neo

Pingchien Neo is the director of international engineering programs at the Herbert Wertheim College of Engineering at the University of Florida. Previously, she taught nuclear engineering courses as a lecturer at UF. Neo discusses what inspired her to pursue nuclear engineering and how that led her toward higher education.

Valorization of steel slag into sustainable high-performance radiation shielding concrete

The disposal of steel slag (SS) has become a serious ecological problem due to the waste of massive land resources. This study reveals the huge potential of recycling SS as heavy aggregates to develop radiation shielding concrete (RSC). The physical characteristics, radiation attenuation capabilities, microstructure, and environmental and ecological impacts of SS-based RSC are comprehensively evaluated and compared with those of normal concrete and the commonly used heavy concrete. The test results indicate that SS-based RSC is prospective to substitute the commonly used heavy concrete, emerging as a sustainable and efficient material for radiation shielding in nuclear energy engineering. Specifically, due to the reaction of cementitious active substances in the surface of SS, the developed SS-based RSC exhibits a fantastic interfacial transition zone (ITZ), and a compact pore structure, thereby showing excellent mechanical properties. The maximum compressive strength of developed SS-based RSC reaches 47.4 MPa. In terms of gamma ray attenuation property, due to the introduction of heavy nuclei and the increase in density, the gamma ray attenuation capacity of developed SS-based RSC is 17.2 % higher than that of normal concrete. The neutron attenuation property is also slightly enhanced due to the refinement effect of SS on pore structure of RSC. Life cycle assessment and unit cost evaluation results demonstrate that compared with barite based-RSC, SS-based RSC can save 97.6 % in cost, 52.0 % in energy consumption, and 70.4 % in carbon emission. The developed SS-based RSC exhibits excellent mechanical properties and radiation attenuation capacities, contributing to the further application of radiation shielding materials. Besides, this approach achieves the high-value recycling of SS, providing new insights for the utilization of high-density solid wastes.

Mathematical Analysis for Optimizing Electro Discharge Machining Parameters and Enhancing Hastelloy Machining Efficiency

This study investigates the process parameter optimisation for Hastelloy electro discharge machining (EDM). The goal of the research is to increase machining accuracy and efficiency by precisely changing the EDM process factors. The most important variables affecting tool wear, surface quality, and material removal rate are identified. In order to improve the machining performance for Hastelloy components, the research highlights the importance of factors including discharge current, pulse duration, electrode material, and dielectric fluid properties. The study's conclusions give important information about how to improve EDM procedures for this tough, corrosion-resistant hastealloy. Extensive research is conducted into the features of tool wear and their connection to process parameters in an effort to increase tool life and reduce manufacturing costs. The findings of this research offer useful data for optimising the efficiency of the Hastelloy EDM process in terms of both money and time. The growing need for high-performance components in industries including aerospace, chemical, and nuclear engineering is being addressed by this study, which intends to lay the groundwork for the development of efficient and environmentally friendly machining practises for Hastelloy. To do this, one must get a thorough comprehension of the interrelationships between the various process parameters.

Nanodiamond Coating in Energy and Engineering Fields: Synthesis Methods, Characteristics, and Applications.

Nanodiamonds are metastable allotropes of carbon. Based on their high hardness, chemical inertness, high thermal conductivity, and wide bandgap, nanodiamonds are widely used in energy and engineering applications in the form of coatings, such as mechanical processing, nuclear engineering, semiconductors, etc., particularly focusing on the reinforcement in mechanical performance, corrosion resistance, heat transfer, and electrical behavior. In mechanical performance, nanodiamond coatings can elevate hardness and wear resistance, improve the efficiency of mechanical components, and concomitantly reduce friction, diminish maintenance costs, particularly under high-load conditions. Concerning chemical inertness and corrosion resistance, nanodiamond coatings are gradually becoming the preferred manufacturing material or surface modification material for equipment in harsh environments. As for heat transfer, the extremely high coefficient of thermal conductivity of nanodiamond coatings makes them one of the main surface modification materials for heat exchange equipment. The increase of nucleation sites results in excellent performance of nanodiamond coatings during the boiling heat transfer stage. Additionally, concerning electrical properties, nanodiamond coatings elevate the efficiency of solar cells and fuel cells, and great performance in electrochemical and electrocatalytic is found. This article will briefly describe the application and mechanism analysis of nanodiamonds in the above-mentionedfields.

Frequency and amplitude of flashing-induced instability in an open natural circulation loop

Several nuclear reactor designs rely on passive containment cooling systems. The so-called containment wall condenser relies on natural circulation loops to extract heat from high-temperature steam in the containment to a water tank at ambient pressure. In such passive systems, phase changes can happen and cause flow instabilities in the cooling loop. The flashing-induced instability occurs when the heated fluid in the riser suddenly vaporizes due to a hydrostatic pressure decrease. This instability causes periodic flow peaks, which are of major concern but whose characteristics have not been studied quantitatively.This paper presents two analytical models that predict the flashing frequency and a maximum flow amplitude from geometry and basic operating parameters such as power level and reservoir temperature. The expressions are derived from a physical analysis and do not involve any calibration constants. The flashing frequency appears to be driven by the power level, the inlet temperature and the riser pipe geometry. For the amplitude, the maximum flow rate can be expressed in a Froude number that depends only on the total pressure losses. These models are validated against PASI experiments and system-scale simulations with the CATHARE 3 code, both performed as part of the European Commission funded PASTELS project. Additional data from numerous experimental studies in the literature are used to extend the validity range of the frequency model.Successfully validated against experimental data and additional simulations, these models provide an explicit relationship between oscillations characteristics and design parameters, making them valuable tools for nuclear engineers.

A numerical method for two-dimensional transient nonlinear convection-diffusion equations

In this research, we have developed the half-boundary method (HBM) for nonlinear convection-diffusion equations (CDEs), which hold significant importance in nuclear power engineering. The HBM employs a variable relationship between the nodes within the computational domain and the nodes located on half of the boundaries. This approach offers notable benefits, includingthe reduction ofthe maximum matrix order and the optimization the maximum memory storage for calculations. Moreover, the HBM is an efficient and streamlined approach to directly handle Neumann boundary conditions, thanks to the utilization of mixed variables. We primarily investigate the memory usage and accuracy of the proposed algorithm in the unsteady-state CDEs, in context of material nonlinear CDEs, the Burgers’ equation and the system of Burgers' equations. The numerical results obtained demonstrate the method’s potential in simulating flow and heat transfer phenomena, particularly in situations where convection is dominant.

Probing deformed nuclei: Experimental insights into excited states of 152,153,154Gd isotopes through fusion-evaporation reactions

The rare-earth region has been the focus of various studies aiming at the understanding of nuclear structure and providing information on the details of the reaction mechanism. The Gd isotopes belong to this group of nuclei and despite the available spectroscopic information, several open questions about their structure still exist, such as the inter-band transitions related to shape evolution or branching-ratios in deformed states. In addition, production cross sections of different reactions to Gd isotopes are largely unknown.In this work, we report on an experimental attempt to populate the excited states in the isotopes 152,153,154Gd by employing the heavy-ion fusion reaction 18O+138Ba → 156-xGd + xn in the 58-64 MeV energy range (center-of-mass). The experiment was conducted at the 9 MV FV Pelletron Tandem at the Horia Hulubei National Institute for Physics and Nuclear Engineering, employing the ROSPHERE array. Several branching-ratios for energy levels in 152,153Gd have been measured, offering new and updated values. Furthermore, relative cross sections regarding the fusion-evaporation reactions 138Ba(18O, 4n)152Gd, 138Ba(18O, 3n)153Gd, and 138Ba(18O, 2n)154Gd have been measured and compared with theoretical calculations with PACE4.

R&D in advanced technology fuels (ATFs) in Spain

Accident Tolerant Fuels, also known as Advanced Technology Fuels (ATFs), have the potential to improve the safety and economic performance of commercial nuclear reactors as well as to provide additional operational flexibility for responding to variations in system energy demand.The design, fabrication and in-pile behaviour of currently operating and innovative nuclear fuels to enable a reliable and safe operation of nuclear power plants is a priority for the nuclear industry. The Spanish nuclear professionals (public and private companies, academia, and research centres) have achieved significant advances in this area. Both irradiation programs in commercial reactors, along with experimental and modelling activities, were focused into comprehending and modelling different ATF concepts to understand and predict the behaviour under normal and off-normal conditions.The International Atomic Energy Agency (IAEA) sub-program “Nuclear Power Reactor Fuel Engineering” is strongly involved in the development and validation of computer codes for ATF fuel design and the valuable Spanish contribution to this sub-program is described in this article.The future Spanish R&D in this field is expected to be focused on further improvements on ATF product development and performance knowledge.

Preface

IOP Conference Series: Materials Science and Engineering International Nuclear Science, Technology and Engineering Conference 2023 (iNuSTEC2023) “Nuclear Science and Technology For Socio-economic Development “ Universiti Tenaga Nasional Kajang, Selangor, Malaysia 10-12 October 2023 MESSAGE FROM: VICE-CHANCELLOR, UNIVERSITI TENAGA NASIONAL (UNITEN)UNITEN is honored to host the International Nuclear Science, Technology, and Engineering Conference 2023 (iNUSTEC2023) and the Nuclear Youth Competition (NYC). With the theme “Nuclear Science and Technology for Sustainable Development Goals”, iNuSTEC2023 is the thirteenth in a series of conferences hosted by the Malaysian Nuclear Society (MNS) since 2010 through collaboration with research institutes and local universities.Don’t we feel like time has passed by so quickly? And with it, came along significant and some were unthinkable changes to our lives. According to Our World in Data statistics, in 2022, each of us consumed on average 3.5 times more energy compared to 40 years ago. In the year 2050, Malaysia is expected to consume almost twice the amount of electricity in 2022 (320 TWh vs. 180 TWh). This means that on a daily basis in 2050, Malaysia is expected to consume close to 0.9 TWh of electricity per day.About 50 million electric vehicles are expected to be on the road in 2050. Every day, about 0.6 TWh of electricity is needed to charge these cars. That is an additional two-thirds of the expected daily electricity consumption per person in 2050. Malaysia has identified the pathways for Responsible Transition 2050 in the National Energy Transition Roadmap (NETR) to tackle the energy trilemma of affordability, security, and sustainability. These pathways include having 0% coal share and 70% renewable energy share of installed capacity in 2050.70% of renewable energy share is about 57 GW of solar PV, which will take a total land size that is slightly smaller than Melaka state. The same amount of power can be generated by nuclear power on a total land size that is 10 times smaller. That is not even considering the intermittency of power generation with solar PV.At UNITEN, we believe that research and knowledge in nuclear power can play a huge role in supporting the Low Carbon Nation Aspiration and the Responsible Transition, especially in providing affordable, clean and safe energy supply to the Rakyat. Institute of Nuclear Energy (INE) at UNITEN was established in May this year to further empower and accelerate the existing research and educational efforts done at UNITEN since 2010.At the university level, UNITEN has established the National Energy Centre (NEC) to support the national energy transition efforts. NEC will serve as a hub for research institutes, industrial and international linkages, and government agencies to form collaborations with experts from local and foreign universities, energy agencies, and stakeholders.UNITEN envisions that NEC will play a significant role in providing technological solutions for Malaysia’s energy transition which will be beneficial to Malaysia, as well as the surrounding region. NEC will also play the role of capacity building for the country’s future workforce that will lead Malaysia towards net-zero in 2050. I extend my warmest invitation to every participant attending this conference, to be a part of this concerted nationwide effort in championing sustainability through involvement with the NEC.I would like to remind participants, that you are among the very small percentage of Malaysia’s population, who are experts in the nuclear field. Thank you so much for your contributions to keeping the knowledge related to nuclear science and engineering alive, despite how hard or negative it can get in the industry.Congratulations to the organizing committee for hosting this iNuSTEC2023 together with the Nuclear Youth Competition (NYC2023). My deepest appreciation goes to our keynote speakers, technical co-sponsors, and all supporters for their contribution to ensuring the success of this conference. To the presenters and participants, thank you for your participation and I wish the conference all success. PROFESSOR IR. DR. NOOR AZUAN ABU OSMAN Vice-Chancellor Universiti Tenaga Nasional List of Editors, Contents, Papers, iNuSTEC2023 Organising Committee, Nuclear Youth Competition 2023 Secretariat, Nuclear Youth Competition 2023, Acknowledgement, Mns Council Members 2023/2025, are available in the pdf.

A Perspective from Ontario Tech University Industrial Research Chairs on 20 Years of Capacity Building in Health Physics and Radiation Science.

Ontario Tech University (University of Ontario Institute of Technology) is one of Canada's newest universities, having been incorporated in 2002. In 20 y, the University has increased enrollment from a few hundred students to over 10,000. The University was designed to be "market driven" and as such offered courses that had high market demand. The Faculty of Energy Systems and Nuclear Science was one of the first faculties to be established at the University, with the intent to fill a gap between personnel that were retiring out of the nuclear industry and the dearth of nuclear engineers and health physicists being educated in Canada. As such, the University established unique programs in both nuclear engineering and health physics/radiation science with strong input from industry stakeholders. This paper will discuss the evolution of the Health Physics and Radiation Science program at Ontario Tech from the teaching and capacity building perspective, and it provides insight regarding health physics and radiation science research at Ontario Tech under the industrial research chair program.

Design and beam dynamics simulation of an 8 MeV compact accelerator-driven neutron source

A compact accelerator-driven neutron source is proposed at Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, called Sun Yat-Sen University Proton Accelerator Facility (SYSU-PAFA). The proton accelerator is composed of a proton electron cyclotron resonance source, a four-vane radio frequency quadrupole (RFQ), and an alternative phase focusing drift tube linac (APF-DTL). It can accelerate 10 mA proton beam to 8 MeV. Due to the high current, beam matching is particularly important. In order to achieve beam matching between various components, beam transport sections are needed. The beam transport line is divided into three segments. The Low Energy Beam Transport (LEBT) ensures that the beam parameters are matched before entering the RFQ. The Medium Energy Beam Transport (MEBT) segment efficiently transfers the beam between the RFQ and DTL. The High Energy Beam Transport (HEBT) focuses on transporting the beam to the targets. The design goal of beam transport line is as short as possible while ensuring high efficiency of beam transportation. SYSU-PAFA has an overall transmission efficiency of 99%, with optimal transverse matching conditions between beam transport and RFQ or DTL accelerators. The efficient use of solenoids and magnets allows for a compact transmission section, resulting in a total length of 13.6 meters, shorter than most accelerators at the same beam energy. This paper will provide the detailed beam dynamics of the compact accelerator.

Design, fabrication and validation of an electrical conductivity principle based two-phase detection sensor array for molten lead (Pb) based heavy metal coolants up to 600°C

Molten lead (Pb) and its alloys (PbBi and PbLi) are of immense interest for various nuclear engineering applications, including but not limited to advanced Lead-cooled Fast Reactors (LFRs), tritium Breeding Blankets (BBs) of fusion power plants and spallation targets for Accelerator-Driven Systems (ADS). Owing to their attractive thermophysical properties, these advanced fluids assert their candidacy to address the critical requirements of neutron multiplication, neutron moderation, high temperature coolants and tritium breeders, enabling the operation of next generation nuclear systems at high temperatures with better efficiencies. However, for numerous reasons such as a compromise of structural integrity at the heat transfer interface, presence of an inert cover gas during charging of molten metal in the loop, and the fusion fuel cycle itself may lead to molten metal-gas two-phase flows with high density ratios. At present, no effective diagnostics exist to detect such operational and accidental occurrences in high temperature molten metal systems resulting in a severe lack of relevant experimental studies. To address these limitations and to advance the current understanding toward two-phase regimes in high temperature Pb-based melts, the present work focuses on the design and assembly aspects of an electrical conductivity-based two-phase detection sensor array, utilizing high purity α-Al2O3 coatings with AlPO4 binder as electrical insulation layers. This paper discusses the design considerations, thermal analysis, systematic selection of structural/functional components along with preliminary results from the probe performance tests in very high temperature (600°C) static molten Pb column for real time detection of argon gas bubbles rising within the melt. Quantitative estimations of time-averaged void fraction, average bubble impaction frequency and average bubble residence time are presented from the preliminary experimental investigations.

Emotional Intelligence of Russia’s Potential Scientific and Technical Elite

A highly intellectual environment involves intense mental activity, rapid acquisition of new material, creativity, competition, and rivalry. All these aspects may cause a long-time neuropsychic stress. Students of leading technical universities need to be able to overcome such difficult situations. The authors reviewed theoretical approaches to emotional intelligence. They designed a psychological model of scientific and technical elite of modern Russia. The model included emotional-volitional, demand-motivational, value-meaning, socio-psychological, and cognitive-activity components. This paper focuses on the empirical study and confirmation of the emotionalvolitional component in potential engineering, scientific, and technical elite, i.e., junior students of Russia’s leading technical universities. The research revealed some psycho-logical peculiarities in their emotional intelligence and coping-strategies. The sample consisted of first-year engineering and technical students of the National Research Nuclear University MEPHI (n = 111). The psychodiagnostic tools included the coping test developed by R. Lazarus and S. Folkman and adapted by T. L. Kryukova, E. V. Kuftyak, and M. S. Zamyshlyaeva; D. V. Lyusin’s test of emotional intelligence. The data analysis relied on IBM SPSS Statistics V.22.0 and the Kruskal-Wallis H-test method of mathematical statistics. The students proved able to consciously analyze difficult situations, work out solutions, plan and predict the outcomes of their behavior, as well as to resort to past experience and available resources. In general, these overcoming models had a constructive effect on the development of an engineer’s personality. However, the underdevelopment of the emotional sphere and poor expression of feelings affected interpersonal and intragroup relationships. Students of nuclear engineering should develop their emotional sphere and expand the range of coping strategies in stressful situations.

Multiscale simulation study on radiation aging of EPDM and preparation of radiation-resistant materials

With the wide application of ethylene propylene diene monomer (EPDM) in the field of nuclear engineering, exploring the radiation aging mechanism of EPDM is of great significance to improve the radiation resistance of EPDM composites. In this paper, the radiation aging mechanism of EPDM was investigated by a combination of experiments and multiscale simulations, and EPDM composites with excellent radiation resistance were prepared. The radiation aging mechanism of EPDM involves the crosslinking and degradation of molecular chains. The aging of EPDM starts from the breakage of α-H in the 5-ethylidene-2-norbornene monomer. In addition, the screening strategy of radiation-resistant additives was proposed. Antioxidants N, N′-diphenyl-p-phenylene-diamine (H), N, N′-ditolyl-p-phenylenediamine (DTPD), and N, N′-di-2-naphthyl-p-phenylenediamine (DNP) were taken as the main research objects, and quantitative analysis was carried out from the aspects of chemical protection and physical protection. The screening results showed that DNP has excellent radiation resistance and migration resistance. The prepared EPDM-DNP composites showed outstanding radiation resistance with 94% tensile strength retention after 300 kGy irradiation. This work contributes to understand the mechanisms of radiation-induced material damage and guides the design of radiation-resistant materials.

Advancing nuclear science education through IRL Integration: A case experiment on criticality mass determination at the Kartini research reactor

Research reactors serve critical roles across multiple domains—from physics to medicine—while distinctly not being used for electrical power generation. The Kartini Research Reactor located in Indonesia exemplifies the integration of research reactors in education and scientific research, particularly highlighting its educational applications through the Internet Reactor Laboratory (IRL). Established in 1978 and operational since 1979, the Training Research and Isotope Production by General Atomic (TRIGA) Mark II reactor is instrumental in advancing nuclear science with facilities like the Lazy Suzan/Rotate Rack and Beam Port. The IRL significantly enhances its educational process, enabling remote access to reactor physics experiments, thus facilitating global university participation in nuclear engineering education. This capability allows for the real-time visualization of reactor operations and detailed presentation of operational data and experiment results, enriching the learning experience. This paper demonstrates the Kartini Reactor's educational utility through a case study investigating reactor criticality and determining the critical fuel mass under safe operational parameters. Employing telecommunication hardware and software, the study achieved reactor criticality by inserting 5 fuel elements, totaling 2524.57 g. The critical mass determination was further refined by plotting the inverse of counts against the total mass of U-235. This approach utilized both polynomial and linear trend lines to analyze the data. While the polynomial analysis provided upper and lower thresholds for critical mass, the linear regression offered a precise critical mass value of 2428.62 g, showcasing a deviation of only 4% from the experimental findings.

Radiation-enhanced precipitation and the impact on He bubble formation in V-Ti-based refractory alloys containing interstitial impurities

V-Ti-based refractory high entropy alloys (RHEAs), e.g., VTiTa and VTiTaNb, have been found with outstanding mechanical properties and irradiation resistance, granting them application potential in nuclear engineering. Nonetheless, similar to conventional V-Ti-based alloys such as V-4Ti-4Cr, these alloys are sensitive to C/N/O interstitial impurities. Under irradiation, such impurities may promote the formation of precipitates which may affect the defect evolution, especially at the appearance of helium. Previous studies have observed different helium behavior in the above alloys, including the heterogeneous distribution of helium bubbles in VTiTa, but the origin was not clear. In this work, detailed microstructural characterization is performed to analyze the irradiation induced precipitates and their impact on helium bubble formation in these alloys. Under helium ion irradiation at 700°C, the TiN precipitates with the NaCl-type structure are formed in all the three alloys. Nonetheless, the interfaces between precipitates and matrix in VTiTa and VTiTaNb are semi-coherent while those in V-4Ti-4Cr are coherent, due to the various lattice parameters of the alloys. Moreover, severe lattice distortion is also found inside the precipitates in the two RHEAs. Consequently, significant heterogeneous nucleation of He bubbles is observed in these two RHEAs but not in V-4Ti-4Cr. Among the three alloys, the growth of precipitates is the fastest in VTiTa, causing the formation of bubble clusters. Furthermore, the growth direction as well as the shape of precipitates affects the shape of bubbles, leading to the {001} cuboids shape in V-4Ti-4Cr and the truncated {110} dodecahedra shape in V-Ti-Ta and V-Ti-Ta-Nb.

Online practical education and training in nuclear engineering: A methodological framework

The education of students in the field of nuclear engineering must combine theoretical and practical teaching, this is the only way to produce quality graduates. Practical education generally includes two areas — experimental teaching and the use of advanced computational codes for the simulation of physical phenomena. The availability of practical education is not a matter of course for all students. The transfer of practical teaching to an online environment opens up a lot of possibilities even for universities that do not have a nuclear reactor, laboratories or extensive computing infrastructure at their disposal.The article deals with key aspects that must be respected when implementing online practical education and training. The listed tips and recommendations are based on the experience gained during the COVID pandemic and during the solution of the PADINE-TT project, which was a response to the development of online teaching and its inclusion in teaching at individual universities.