Field Of Nuclear Energy Research Articles

Highlights and outlook of the Dutch PIONEER 2021–2024 R&D program

The Netherlands has a prominent infrastructure in the field of nuclear energy and medical applications. At present the country operates one nuclear power plant, but with an ambition of extending the lifetime of the current nuclear power plant beyond 60 years and construction of two further nuclear power plants in the coming decade. In addition the country plays a significant role in the enrichment of nuclear fuel with two enrichment plants operated in the east of the Netherlands. Furthermore, the Netherlands is the largest producer of medical isotopes in the world, and has some world renowned medical institutes in the field of nuclear medicine. To compliment this infrastructure the Netherlands also contributes to nuclear innovations, through international research and development (R&D). This paper will provide an overview of the Dutch nuclear infrastructure, and it will present the publicly financed R&D program PIONEER which forms the backbone of nuclear research in the Netherlands. The seven intertwined themes of program will be described, together with a single highlight per theme. The paper will also give an outlook on the expected directions for research for the period’25 to’28. Whereas many of the current topics are expected to remain important for the future multiannual program, the plans for expansion of the nuclear power capacity in the Netherlands will lead to a broadening of the scope to support realization of new nuclear power plants in the country, deployment of water-cooled small modular reactors and developments in advanced reactors.

Development of granular composites based on laponite and Zr/Fe-alginate for effective removal of uranium (VI) from sulfate solutions

The object of research is granular composites based on zirconium-iron alginates and laponite. The task of research is to determine the influence of the Zr:Fe ratio on the structure of granular composites and efficiency of uranium (VI) removal from aqueous solutions. The influence of the zirconium and iron ratio on the parameters of the material's pore structure has been established, particularly on the change in the content of micropores within the matrix. The specific surface area of the materials ranges from 86 to 112 m²/g. The sorption properties of the composites regarding uranium (VI) have been investigated. The impact of the charge of surface groups and the form of uranium (VI) presence in sulfate solutions on their sorption characteristics has been demonstrated. The maximum adsorption capacity reaches 265.1 µmol/g at pH 6. It is shown that an elevated electrolyte content positively affects the efficiency of uranium (VI) removal in neutral and alkaline medium. It has been established that structural changes in the materials occur due to the intensive interaction of iron ions and alginate molecules, resulting in the formation of a dense gel-like structure. The mechanism of uranium (VI) removal is associated with the formation of surface complexes in the presence of electrolytes. The synthesized granulated composites exhibit improved removal efficiency of uranium (VI) under conditions of high mineralization of solutions, making them attractive for potential use as sorbents. The obtained results can be utilized in the development of effective methods for purifying water environments from uranium (VI) in high mineralization conditions, which is a relevant issue in the field of nuclear energy and the removal of radioactive substances from water systems

Artificial intelligence and machine learning applications in the Spanish nuclear field

Machine Learning and Artificial Intelligence techniques are increasingly applied in the nuclear field. In this way, Spanish companies and research institutions have been developing different projects in the field of nuclear energy applying such techniques. A brief overview of some of these projects is presented, which cover areas as diverse as nuclear data, nuclear fuel manufacturing, simulation codes, fuel performance monitoring, nuclear inspection, and operation training. Among the techniques used to develop them are deep neural networks for building surrogate models, convolutional neural networks for computer vision, Bayesian networks and Gaussian processes for predictive models, and speech recognition with large language models.

Clean and efficient Zr/Hf(Ⅳ) separation system constructed by bisamide ionic liquid

Nuclear energy is an indispensable clean energy. We design a new type functional ILs [(RNCO)2Cn·H]2[MCl6] (M = Zr,Hf) by using the green solvent bisamide to separate the key metals Zr(IV) and Hf(IV) of nuclear energy field [(RNCO)2Cn·H2][Cl]2 was obtained by protonation reaction of bisamide (RNCO)2Cn, it can be used as an ionic liquid (ILs) to provide a cationic center [(RNCO)2CnH]+, but also has a dual function as a solvent. The ionic liquid (ILs) [(RNCO)2Cn·H]2[MCl6] can be rapidly formed by [(RNCO)2CnH]+ and transition metal anions ZrCl62−/HfCl62− in an acidic chloride system at a room temperature. From the perspective of material energy and frontier molecular orbital (FMO), it is confirmed that [(RNCO)2Cn·H]2[MCl6] is formed by an anion association mechanism [(RNCO)2Cn·H]2[MCl6] can be stable in organic solvents when contacting with a high concentration acidic chloride system. At the same time, the ILs have high thermal stability that decomposes temperature above 300 °C. It is surprising that separation and purification of Zr/Hf(Ⅳ) can be done efficiently via the different stability of anion centers formed by Zr/Hf(Ⅳ) in acidic chloride systems. When the concentration of (RNCO)2Cn is 25 %, the separation coefficient of Zr(IV) and Hf(IV) can reach 11.4. And this work proposes the concept of recycling of organic solvents and acidic solutions, which provides an effective research idea for the clean production of nuclear energy metals.

Prediction of state transitions in 3D core dynamics and xenon transients based on dynamic mode decomposition

This study proposes a method based on Dynamic Mode Decomposition (DMD) for predicting the state transitions of core dynamics and xenon transients in nuclear reactors. Both types of transients, occurring at different time or spatial scales, have significant impacts on the stability and safety of nuclear reactors. The DMD method is employed to model and predict the transient behaviors in nuclear reactors. DMD is a data-driven model simplification technique that extracts the dynamic modes, i.e., characteristic patterns, from time-series data. By applying DMD to the data of core dynamics and xenon transients, we obtain the characteristic modes of the system under different states, which are then used for predicting state transitions. Simulation experiments are conducted using the benchmark problems of the 3D LWR transient cores provided by NEACRP. The results demonstrate that the DMD-based method effectively predicts the state transitions of core dynamics and xenon transients in nuclear reactors. The accuracy and reliability of the method are validated through the analysis and comparison of predicted results with actual data. Additionally, the impact of model parameters on prediction performance is investigated, and optimization strategies are proposed to further improve the prediction results. The findings of this study offer a novel approach and insights for predicting transient behaviors in the field of nuclear energy.

The applicability of the Polluter Pays Principle in the field of nuclear energy in the EU

This article will examine whether the Polluter Pays Principle is formulated and applied in EU versus nuclear (Euratom) law and what consequences such application could have for the EU Member Countries, e.g., when deciding on new nuclear projects or life time extension of nuclear installations. The ECJ had already clearly accepted the Polluter Pays Principle’s function of internalization of all environmental costs. It is crystal clear that EU Institutions are required to apply the PPP, together with the Precautionary and the Proportionality Principles. The application of the PPP in the nuclear field has been emphasized in an EU Commission Recommendation of 24 October 2006. On the other hand, with Council Directive 2011/70/EURATOM of 19 July 2011, a Community framework for the responsible and safe management of spent fuel and radioactive waste was launched. In its Article 5(1) the duty to establish and maintain a national framework was formulated, but no mention is made of the application of the PPP, not in this Directive nor in the national reports and the EU follow up reports. The terminology used therein, ‘adequate financial resources’, falls short of an unambiguous adherence to the Polluter Pays Principle. The PPP should hold that ALL costs for decommissioning, waste conditioning and final disposal should be carried by the polluter. A cap on the nuclear waste costs as decided in Belgium seems to be in full contradiction with the earlier decisions of the ECJ and with the EU Commission’s Recommendation of 2006. Furthermore, the EU General Environmental Principles are made applicable to the nuclear energy sector by the ECJ in the Hinkley Point C case. As argued in the present article, the Polluter Pays Principle will be a heavy burden to bring the EU legal acquis in line with all the uncertainties on the costs of closing the cycle of nuclear energy production. Accepting a ‘cap’ on the nuclear waste costs leaves a blank cheque for later generations, which is not only against the Polluter Pays Principle, but is also completely in contradiction with the EU Green Deal regarding fair competition in the field of energy production and limiting the effect of subsidies for costs which have to be borne by the nuclear waste producers.

Highly selective monitoring of trace radioactive I2 over organic iodides using NH2-DNA based electrochemiluminescence device

The selective determination of radioactive I2 over organic iodides is beneficial for the efficient treatment of spent fuel and nuclear emergency. We herein develop an efficient strategy for trace I2 selective detection over organic iodide for the first time by using electrochemiluminescence (ECL) device. In detail, an I2 selective sensor is prepared by Au nanoparticles and dsDNA with -NH2 group, and then modified on indium tin oxide (ITO) electrode to obtain I2 detection device. -NH2 acts as ECL co-reactant as well as I2 selective response group, which can specifically combine with I2 in organic iodide atmosphere to quench the signal of ECL emitter (Ru(bpy)32+). This device gives a low limit of detection (5 ng/L) and high selectivity to I2 under high humidity, acidity, temperature as well as CH3I atmosphere. ECL imaging technology is applied to realize visualized accurate monitoring to trace I2 in atmosphere. Electrochemical measurement and theory calculation are further employed to demonstrate the selective mechanism of I2 detection over organic iodides. This work provides an efficient strategy and device for trace I2 specific monitoring, which exhibits a promising prospect in the fields of environment and nuclear energy.

Graphene oxide composited with different size of organic molecules for hydrogen isotopic water separation in membrane distillation

Developing an efficient light water/tritiated water (H2O/HTO) separation process to meet environmental regulations is important in the nuclear energy field. The membrane distillation processes for the separation of H2O/D2O (deuteriated water), which is usually served as the laboratory model process for H2O/HTO separation, showed good separation performance with graphene oxide (GO)-based membranes. Here, the approach to enhance the H2O/D2O separation performance was explored through regulating interlayer spacing and physicochemical properties of membranes, for which two types of GO membranes were prepared and applied in air-gap membrane distillation: (i) small molecules of urea (UR) or ethanediamine (EDA) were cross-linked with GO platelets to obtain GO-framework (GOF) membranes designated as GO-UR or GO-EDA with varied interlayer spacing. The GO-EDA membrane with a permeation flux of 0.95 L·m−2·h−1 gave higher separation performance than the pristine GO membrane; (ii) macromolecules of hydrophilic polyvinyl alcohol (PVA) or hydrophobic polymethyl methacrylate (PMMA) were intercalated into GO laminates to adjust interlayer spacing and physicochemical properties of membranes. The resultant GO-PVA membrane exhibited a higher permeation flux of 0.94 L·m−2·h−1 and similar separation factor compared with the pristine GO membrane. Moreover, long-term process stability of H2O/D2O separation in membrane distillation was demonstrated using GO-EDA membrane for a 28-h process. Therefore, the results demonstrated that regulating interlayer spacing and physicochemical properties of membranes can provide a facile route to improve performance of GO-based membrane distillation processes for the separation of H2O/D2O, which may be applied to H2O/HTO separation process needed for the treatment of tritiated water in the nuclear energy field.

Core nuclear design and heat transfer analysis of a megawatt-level SiC coated particle based vehicular micro reactor

As a versatile and diversified source of new energy, transportable micro reactors can offer high flexibility and the ability to provide power services even in remote areas. When utilizing coated fuel particles and supercritical carbon dioxide (S-CO2) coolant, the transportable micro reactor core achieves exceptional inherent safety and high power generation efficiency, rendering it incredibly competitive within the nuclear market. The Vehicular Micro Reactor (VMR) previously investigated is an integrated micro-reactor cooled by S-CO2, which employs TRistructural ISOtropic (TRISO) fuel particles dispersed in a conventional graphite matrix to generate 5 MW of power output. However, its drawback lies in the low fuel loading capacity. In recent year, the application of high-strength SiC materials in the field of nuclear energy has been developing continuously. In this paper, a new type of double-layered SiC coated fuel particle is designed, based on which a SiC-based Vehicular Micro Reactor (SVMR) is proposed and explored. It represents an improved design of VMR, with the main difference being its utilization of SiC as a matrix and filling by the two-layered SiC-coated fuel particle to achieve higher fuel loading than the VMR. In this paper, both the neutronic and heat transfer characteristics of the SVMR are discussed. The neutronic simulation is conducted using SCALE code based on Monte Carlo method, the module KENO IV was used to analyze the effective neutron multiplication factor (keff), and SCALE/TRITON (Transport Rigor Implemented with Time-Dependent Operation for Neutronic Depletion) coupled by 2-D radiation transport code NEWT and ORIGEN for burn-up calculation. By optimizing the assembly size and SiC-coated fuel particle size, the SVMR core achieves high fuel loading capacity and superior fuel utilization efficiency. The results of the heat transfer analysis also demonstrate that the SVMR core, which is entirely SiC-based, exhibits exceptional heat transfer capability. The excellent neutron economy and inherent safety make SVMR a more competitive micro reactor concept.

Research and analysis of new generation nuclear reactors in the world

The research of new nuclear reactors is gaining urgent importance worldwide due to the need for continuous improvement of technologies to ensure safety, efficiency, and emissions reduction. This is crucial in the context of climate change and rapid technological development, which demand constant updating and improvement of nuclear energy. The objective of the study was to analyse next-generation reactors worldwide and identify their advantages and potential prospects for the future. The research utilized statistical, comparative, and analytical methods. The results of the analysis considered contemporary technological and safety parameters related to the operation of such reactors, including their ability to optimize fuel usage, enhance operational safety, and effectively manage radioactive waste. As a result of the study, fourth-generation nuclear reactors were analysed, including fast neutron reactors using gas cooling, very high-temperature reactors, reactors using sodium as a coolant, fast neutron reactors with lead cooling, reactors where the reaction occurs in molten salt, and supercritical water-cooled reactors. Each of these reactors has its unique features that make them distinctive in their application. For example, gas-cooled reactors have high productivity due to their ability to achieve high temperatures without significant pressure. On the other hand, molten salt reactors offer flexibility in using different types of fuel, including spent fuel, and can help reduce the level of radioactive waste through the use of special materials. During the analysis, it was noted that fourth-generation reactors, using various cooling and reaction-slowing technologies, are characterized by high efficiency, low accident risk, and the ability to produce stable electricity. Improved methods of reaction control open up new possibilities for the efficient production of electricity and increased safety in nuclear energy. The practical significance of the research lies in the opportunity to enhance modern electricity production technologies and ensure greater safety and efficiency in the field of nuclear energy

The emergence of quantum energy science

Quantum engineering seeks to create novel technologies based on the exploitation of distinctly nonclassical behaviors such as quantum coherence. The vast majority of currently pursued applications fall into the domain of quantum information science, with quantum computing as the most visible subdomain. However, other applications of quantum engineering are fast emerging. Here, we review the deployment of quantum engineering principles in the fields of solar energy, batteries, and nuclear energy. We identify commonalities across quantum engineering approaches in those apparently disparate fields and draw direct parallels to quantum information science. We find that a shared knowledge base is forming, which de facto corresponds to a new domain that we refer to as ‘quantum energy science’. Quantum energy science bears the promise of substantial performance improvements across energy technologies such as organic solar cells, batteries, and nuclear fusion. The recognition of this emerging domain may be of great relevance to actors concerned with energy innovation. It may also benefit active researchers in this domain by increasing visibility and motivating the deployment of resources and institutional support.

Design and coherent strengthening of ultra-high strength refractory high entropy alloys based on laser additive manufacturing

The WNbMoTa-based refractory high entropy alloy (RHEA) is expected to become a new generation of high-temperature materials due to its high thermal stability, which can be used in aerospace, nuclear energy and other fields. In this paper, TN10 (TN is the abbreviation of Ti and Ni elements), TN15, TN20 and TN25 non-equimolar WNbMoTa-based RHEAs were designed based on phase engineering and formed by laser powder bed fusion (LPBF) technology. The solidification thermodynamics, microstructure and mechanical properties (compressive strength at 25 °C) of the four alloys were analyzed, and the strengthening mechanism of TN20 alloy was studied. The compressive yield strength of the four alloys exceeds 2050 MPa, the ultimate compressive strength exceeds 2550 MPa, and the elongation exceeds 9%. The compressive yield strength of TN20 alloy is 2513 MPa, the ultimate strength is 3127 MPa, and the elongation is 11.38%. The room temperature (25 °C) compressive yield strength of TN20 alloy is the highest among the high entropy alloys studied so far. TN20 alloy is composed of BCC matrix phase and grain boundary phase containing three different structures, which are B2 TiNi phase, Ni55Nb25Ti15Ta5 phase generating stacking faults and Ni70Ti20Nb10 secondary precipitated phase. The micrometer matrix phase and nanometer grain boundary phase of TN20 alloy show a network distribution in fine crystal region. After the matrix phase cracks due to high thermal stress, the flow TiNi-rich grain boundary phases precipitate to fill the cracks. The grain boundary phase with high proportion in this region is enhanced by the secondary phase and its nanoprecipitated phase. In other regions, stacking faults are generated by the Ni55Nb25Ti15Ta5 phases, which convert the thermal stress that induces crack into lattice defects of the crystal. On the other hand, the content of B2 phase is the highest in grain boundary phase, and the grain boundary between B2 phase and matrix phase is a coherent grain boundary, which realizes the high quality combination of grain boundary phase and matrix phase. The design and strengthening of WNbMoTa-based non-equimolar RHEAs are studied in this paper, which is expected to provide a reference for the design of a new generation of high entropy alloy.

The role of the IAEA in establishing international standards for the use of atomic energy (retrospective analysis)

Paradoxically, the peaceful use of nuclear energy and all the prospects it opens up for humanity often coexist with the prospect of nuclear proliferation and nuclear war. This difficult perception is understandable: the materials, knowledge, and expertise needed to produce nuclear weapons are generally no different from those needed to produce nuclear energy and conduct nuclear research.Therefore, ensuring the peaceful and safe use of nuclear energy has always been in the center of attention of the international community. The approach is determined by a complex of national and international measures. It is generally accepted that the primary responsibility for regulating the use of nuclear energy rests with national authorities, but it is also clear that other countries may also be affected. Thus, like many other human activities with potentially transboundary consequences, nuclear energy regulation requires a residual, and in some cases joint, responsibility on the part of the international community to ensure the harmonization of standards, coordination and pooling of resources and services, and regulatory cooperation this activity.In this regard, the IAEA and other international and regional organizations play the role of coordination centers. Article II of the IAEA Statute states that the organization shall seek to accelerate and increase the contribution of atomic energy to world peace, health and prosperity and shall provide, as far as possible, assistance upon request. IAEA supervision or control shall not be used to achieve any military objective.International peration in the field of nuclear energy over the past six decades has resulted in legally binding norms and advisory standards and regulations. This article outlines this global legal framework for the safe and peaceful development of nuclear energy. In particular, it concerns nuclear safety, radiation protection, radioactive waste management, transportation of radioactive materials, emergency assistance and planning, civil liability for nuclear damage, physical protection of nuclear material, armed attack on nuclear facilities, safeguards and controls carried out and provided by the IAEA.

Design of Microbial Corrosion Assessment Model for Protective Coatings based on Combined Weight TOPSIS

Instrumentation has a wide range of applications in various fields. In today’s rapid development of information technology and the economy, it plays an indispensable role. The application environment of instrumentation in many fields is complex and harsh. Therefore, the requirements for instrumentation materials are also more stringent. This paper mainly focuses on the special fields of aerospace, petrochemical, marine, and nuclear energy. The application status of instrumentation and its harsh application environment have been researched. This paper researched the main corrosion failure modes of instrumentation materials, and put forward suggestions and solutions for corrosion protection methods.

Multi-objective optimization design of TRISO-based fully ceramic microencapsulated fuel

Fully Ceramic Microencapsulated (FCM) fuel is a new type of material in nuclear energy field. It has become a promising accident tolerant fuel (ATF) candidate due to its advantages of high radiation stability, high fission product containment capacity and excellent thermo-mechanical performance. During operation, the temperature, stress, deformation and other key parameters will change significantly, which directly affect the safety of nuclear reactor. Therefore, it is necessary to carry out a multi-physics fully-coupled analysis suitable for the multi-scale, multi-component, multi-phase and nonlinear coupling processes in the reactor, so as to sort out the influences of material properties, radiation behavior, thermo-mechanical performance from numerous influencing factors. In this paper, based on the irradiation-thermo-mechanical coupling method, the performance of TRISO-based FCM fuel under irradiation conditions was analyzed, key thermo-mechanical parameters and other influencing factors of the fuel were obtained, failure behavior of the fuel element was evaluated. On this basis, the theoretical and numerical model of multi-objective optimization method were established, the optimum parameters including material properties, fuel geometry and particle arrangement were found by optimization method. The optimization results showed that the multi-objective optimization results could provide multiple Pareto optimal solutions for the FCM fuel. Specifically, when the TRISO particle spacing is 200 µm and 150 µm, the objective function difference between the optimal heat transfer solutions is only about 1.7%, meanwhile the mechanical properties vary significantly (the difference between the objective functions of the optimal solutions is about 12.4% ∼26.5%), indicating the response of stress is more sensitive than temperature. When the TRISO particles are tightly packed (particle spacing less than 100 µm), the difference of objective function between the optimal solutions is less than 5%, illustrating the optimization has limited improvement on the thermo-mechanical performance of the fuel, namely the optimization space is limited.

Burnup-control drum coupling characteristics investigation of lead–bismuth eutectic-cooled solid reactor

As an advanced research tool, neutronics and thermal-hydraulics coupling have a wide range of promising applications in the field of nuclear energy. This paper develops a burnup-control drum coupling code based on the Monte Carlo code RMC and the computational fluid dynamics (CFD) program STAR-CCM +. The dynamic adjustment of the control drums' position and more realistic prediction of reactor neutronics and thermal-hydraulics is achieved by updating the nuclide density, solving the control drum value function and updating the neutronics model in the process of burnup calculation. The core of a lead–bismuth-cooled solid reactor was also studied to investigate the neutronics and thermal-hydraulics properties of the solid core when the effective multiplication factor was kept at about 1.0, and the core's power and temperature variation patterns during the lifetime were obtained. The results of the study show that the simulation of the coupling code achieves the design purpose. In addition, the solid core's maximum fuel and cladding temperatures decrease with the deepening of the burnup.

Soviet Response to the European Atomic Energy Community (Euratom)

This article discusses the way the USSR reacted to the creation of the supranational European Atomic Energy Community (Euratom). The authors believe that the Soviet criticism of German and French nuclear programs was, at least, partially, objective and non-ideological. The study featured documents on Soviet foreign policy that described the initial reaction of the USSR to the Euratom plans, suggested alternative options for European cooperation in the field of peaceful nuclear energy, and showed the evolution of the Soviet approach to European integration. Western Europe and the United States had their own goals in the development of the peaceful nuclear industry in Europe. The fears expressed by the USSR were related to the membership of the Federal Republic of Germany in Euratom and the role the United States intended to assume in this organization. Eventually, Moscow accepted a more neutral position in relation to the Euratom and other integration processes in Western Europe.

DEVELOPMENT OF NUCLEAR ENERGY IN THE REPUBLIC OF KAZAKHSTAN: ISSUES AND TRENDS

Purpose of the research is to study the level of public awareness, transparency and trust in the authorities in the framework of the state policy for the construction of a nuclear power plant.Methodology. In this work, both qualitative and quantitative research methods are applied. The study uses an online sociological survey among the population to analyze the impact of the ongoing state policy on the energy security of the country, namely the construction of nuclear power plants. In this work, an online survey based on a Google Survey was used. The survey involved 108 respondents. Also presented in the work are information materials of state institutions, information and news articles, as well as a review of international experience in the field of nuclear energy. Also, for the analysis and evaluation of external factors for developing nuclear energy, we considered PEST-analysis (Political, Economic, Social, and Technological factors).Originality / value of the research. Society plays an important role in solving the most urgent and acute political issues in the country. The awareness and opinion of citizens contributes to the development in society of a positive attitude towards the political decisions made in the state. Over the past two decades, in some countries, policies to reduce energy costs and targets for reducing greenhouse gas emissions have contributed to the introduction of clean energy, including nuclear energy. In Kazakhstan, the issue of energy security has always been relevant and has never been removed from the agenda. Today, despite all the eff orts of the state, problems in the energy sector are not decreasing.Findings. This paper analyses the statements of many authors who believe that the degree of public awareness depends on the transparency and informational openness of state bodies. A sociological study was used in this work in order to empirically prove the influence of these factors. The survey contains the answers of the respondents. The analysis turned out to be quite interesting. As a result, the presence of a positive relationship between the level of information provided by state institutions and the awareness of citizens has been clearly demonstrated.

A Review of Corrosion Behavior of Structural Steel in Liquid Lead–Bismuth Eutectic

Liquid lead–bismuth eutectic alloy is one of the candidate coolants for fourth-generation nuclear power systems because of its good physical and chemical properties, neutron economic performance, and safety. However, the compatibility between the coolant and structural steel is still the main factor restricting its large-scale industrial application in the nuclear energy field. Structural steel in a liquid lead–bismuth eutectic alloy for a long time would cause severe corrosion. The erosion of structural steel by high-flow-rate liquid lead–bismuth alloy will lead to a more complex corrosion process. This paper mainly reviews the corrosion characteristics of liquid lead–bismuth and the corrosion behavior of structural steel in liquid lead-bismuth eutectic. The main methods of inhibiting liquid lead–bismuth corrosion are summarized, and future research directions are suggested.

Automation of the procedure for determining the admissibility of erosion- corrosion wear in pipelines of nuclear power plants made of carbon steels

Many pipelines in Ukrainian nuclear power plants have been in operation for over 30 years, and the determination of the admissibility of erosion-corrosion wear (ECW) defects in the pipeline wall metal is currently one of the pressing issues in the nuclear energy sector of Ukraine. A comparative analysis of determining the admissibility of pipe wall thinning due to ECW was conducted using the adopted methodology “MT-T.0.03.224-18” by the State Enterprise “Energoatom” and the guidance based on the use of regulatory documents for designing pipeline elements. The use of the methodology demonstrated significant advantages in terms of reducing the conservatism of ECW assessment, especially for small-scale thinning and pipelines operating at pressures below 60-80 kgf/cm2, which allows for a substantial reduction in repair work. However, the implementation of the methodology in practice may encounter difficulties due to the complexity and labor-intensiveness of the calculation assessment procedure for nuclear power plant personnel. Therefore, to automate the ECW admissibility assessment in accordance with the methodology requirements, software (SW) was developed for use by nuclear power plant personnel, enabling the prompt generation of a protocol for the express assessment procedure of ECW admissibility for a straight section of the pipeline based on the measurement results of wall thinning parameters in the axial direction. The software allows for concluding whether the section can be put into operation, sent for repair, or requires further refined assessment. Additionally, software based on the finite element method (FEM) was developed, which, when necessary, allows for a refined assessment of a straight section, taking into account the depth and angle of thinning in the circumferential direction, and calculates the stress of the limit plastic state of the pipeline section with ECW from the perspective of viscous fracture. The devel- opment is applicable in the field of nuclear energy in Ukraine.