Search

Inconel 718 is designed for high tensile and yield strength and can sustain its properties under high or low temperatures. These properties make it suitable for industries like, turbines manufacturers, aviation industry and nuclear power plants. However, it is categorized as difficult to cut material, as such materials possess behavior of ductility, work hardening and production of enormous heat and abrasion during machining. This makes the machinability of Inconel 718 a challenging trade as dimensional accuracy is difficult to achieve. This result in wastage of material, more power consumption and resources required. To explore the machinability and cater the green manufacturing issues of Inconel 718, in this study, the surface roughness (Ra) of sculptured surface is analyzed. For detail and robust analysis, experiments were performed under dry and wet conditions. For both conditions, coated solid carbide ball end mill were used in CNC milling. Effect of cutting parameters like cutting speed, depth of cut and feed were studied using Taguchi techniques for enhanced surface finish. Analysis of variance (ANOVA) was also performed to determine the significant factor that affects surface finish. Regression analysis were performed and surface finish models were developed to estimate the surface finish prior to machining. This study is not only valuable for better-quality machining of Inconel 718 (curved surfaces) but also for its process and environmental sustainability. [ABSTRACT FROM AUTHOR]

Security system of nuclear facility must be reliable and robust so it must be built and designed using genuine equipment and components. The use of counterfeit, fraudulent, or suspect items (CFSI), whether intentional or unintentional, in the security system will threaten and endanger the security system itself so that it requires careful addressing of CFSI. CFSI are a major concern today, especially in nuclear facilities. They can pose a direct and potential threat to security, in addition to the safety, performance of the facility, the public and the environment, and they can have a negative impact on the cost of the facility. Supply chains and procurement processes play a role in detecting and preventing the entry of CFSI, or substandard non-conforming goods, into nuclear facilities. Lack of control of the processes involved in procuring, receiving, using or disposing of goods can lead to the entry of CFSI into nuclear facilities. This can lead to unexpected threats. Procurement must be managed effectively to ensure the availability of design functions throughout the service life of the nuclear facility. This paper will explore and identify laws and regulations, regulatory challenges, and see the adequacy of these regulations in the context of addressing CFSI in the construction of nuclear security systems in Indonesia. The method used is descriptive and qualitative analysis as well as literature study. The results of the review show that although there are no laws or regulations specifically aimed at regulating matters related to counterfeit goods, in principle, nationally there are already existing regulations concerning the circulation and trade of counterfeit goods. However, the specific regulations on CSFI in the nuclear industry still have to be further regulated in a more complete national regulation. [ABSTRACT FROM AUTHOR]

The paper describes the role of atomic energy in the energy balance and the nuclear industry development strategies of countries. The development problems of the Russian nuclear industry, which is the most important condition for ensuring energy independence and stable growth of the country's economy, have been identified. The paper describes the specifics of atomic energy, its strengths and weaknesses, as well as risks and opportunities. A brief overview of the theoretical fundamentals of the modern theory of clusters and various scientific approaches to the concept of a cluster is given, the domestic nuclear industry development specifics are shown, and the existence of the nuclear industry cluster in Russia, its effective functioning, and successful development is justified. The mechanism of state management and financial support of the nuclear industry cluster has been formulated, and the role of its research complex in the Russian nuclear industry development has been determined. The expediency of improving the mechanism for managing and funding the research complex of the nuclear industry cluster using the model of creating a state fund for supporting scientific, research, and innovative activities in the field of atomic energy has been justified, which, among other things, will improve the efficiency of budgetary expenditures. [ABSTRACT FROM AUTHOR]

The discrete element method (DEM) is an increasingly popular computational technique applied across various industries. It has enabled tremendous advancements in simulating integrated bulk material handling systems for treating hazardous materials. While DEM provides a safe and cost-effective alternative to manual testing, there is little published research regarding its application in the nuclear industry. This study provides an overview of the application of DEM in examining a unique dust-containing filling nozzle for filling the Idaho calcine simulant into a straight-wall canisters for hot isostatic pressing (HIP). It concludes that the validated contact model can accurately emulate the filled bulk density and surface profile formed by the bulk material inside the HIP canister. The simulation model offers insights into the interaction between the bulk materials, the filling nozzle, and the HIP canister, which are valuable for designing HIP canisters and optimizing the filling conditions. This paper aims to provide a validated contact model, which can be adopted by future research to accelerate the development of new engineering solutions for treating the Idaho calcine waste. [ABSTRACT FROM AUTHOR]

GRE@T-PIONEeR - GRaduate Education Alliance for Teaching the PhysIcs and safety Of NuclEar Reactors - is a project funded by the Euratom – Horizon 2020 Framework Programme which aims at developing and providing specialised and advanced courses in computational and experimental reactor physics at the graduate level (MSc and PhD levels) and post-graduate level, as well as the staff members working in the nuclear industry. One of the work packages of GRE@T-PIONEeR is devoted to developing a specific course on the nuclear data pipeline processes and to present the role of nuclear data to play in calculations of innovative reactor systems. This course covers all steps in the nuclear data life cycle, starting from the measurements to their validation and final use in nuclear reactor calculations. Beyond the technical contents of the courses being developed, the paper describes the use of innovative pedagogical methods and active learning techniques, such as flipped classes, aimed at promoting student learning. [ABSTRACT FROM AUTHOR]

Fission yields are of major interest for the nuclear industry and the study of the fission process. Fission yields are determined by evaluation process based on the analysis of experimental datasets and completed by phenomenological models. The aim is to provide the best estimation of independent yields of 235U(nth,f) reaction. In this paper, we will focus on the methodology of assessment of the nuclear charge distribution per mass. In the JEFF-3.1.1, the Wahl's parametrization of the Zp-model is used to complete the experimental knowledge. Nevertheless, the lack of this parametrization consists in the absence of uncertainty information. Consequently, it is impossible to generate the components of independent yield correlation matrix from the Zp-model. In this context, we propose to use the Zp model with a new parametrization to assess the charge distributions. Two different calculations have been developed: the first one is based on a Wahl-like linear approximation of the parameters as a function of mass. The second approach consists to apply a "direct-Zp model" without linear assumptions. This analysis is achieved using the Markov-Chain Monte-Carlo (MCMC) method to adjust the model parameters and then to deduce the covariance of charge distributions. Moreover, with our development, we have directly and consistently described the pre-neutron and post-neutron charge distributions. [ABSTRACT FROM AUTHOR]

Austenitic Stainless steel finds wide applications in industrial as well as domestic usage. Because to its outstanding physical characteristics as well as mechanical and chemical properties, Austenitic stainless steels are being largely utilized for architectural applications such as water and fire features, coil material and equipments for vaporizers, mining, chemical, cryogenic, food, dairy and pharmaceutical industries atomic industries etc. Different welding processes have been successfully implemented for welding different variants of Austenitic stainless steel. In this paper, various welding techniques which have successfully utilized to weld different grades of austenitic stainless steel have been thoroughly reviewed. [ABSTRACT FROM AUTHOR]

The environmental method ideally suited for eco-systems and the potential to manage a cycle efficiently and continuously is characteristic of sustainability. Sustainability in all respects is the secret to the long-term survival of the human race. Recent energy shortages and global climate change issues have prompted people to look at the benefits and dangers of nuclear energy and to find a viable solution. The risk of fatal accidents and the long-term management of radioactive wastes undoubtedly limit nuclear energy advantages such as no greenhouse gas emissions and a large amount of minimal infrastructural power supply. Since nuclear power is a matter of balancing gain and risk, this document summarizes the advantage and danger of nuclear power for potential energy demand to be sustainable. Robotic systems offer the perfect solution to some of these issues, eliminating the need for humans to access these sites and also providing data on the status of those sites that would otherwise not be available. However, the requirements of a given robot are often very different, and the precise characteristics of a particularly tough environment pose considerable challenges even for the most robust of the platforms. Besides, such developments can be costly and time-consuming. [ABSTRACT FROM AUTHOR]

The proposed computer system implements a scheme of joint - classroom and distance learning, scientific and exploratory research in order to motivate and stimulate students' independent work in acquiring professional competencies. The developed system reflects both the traditional structure of education in universities using groups of students, specialties and curricula, as well as modern trends in the transition to distance learning, i.e. the opportunity to study at any time and in any place, according to individual plans and schedules. The presented development can be used by students to acquire and develop competencies in the field of improving and managing technological processes for the production of metal products, including the design of machines and metal structures for additive technologies. This is ensured both by the created (and permanently updated) database of mechanical and technological characteristics of steels and alloys used in the production of materials for special purposes, including for the nuclear power industry and the chemical industry, product quality and environmental safety, and by programs developed on based on author's methods and implemented in the system of distance education, in particular, for calculating the modes of shaping and energy-power parameters in the formation of metal products. [ABSTRACT FROM AUTHOR]

In this paper, a method of analytical studies of heat-resistant alloys under conditions of their unsteady thermal conductivity is proposed. Such problems arise when designing structural elements that are exposed to prolonged exposure to high temperature during operation, the value of which varies over time. This has recently become particularly relevant in connection with the achievements made in the nuclear industry and thermal power plants operating with steam turbine installations. To study the above processes, the paper considers a mathematical model of a rod of finite length. This became the basis for the creation in the future of a program in the programming language, with the help of which it is possible to construct the corresponding fields of temperature distribution, all the components of deformation, stress and displacement in the form of graphs. The obtained models make it possible to take into account internal heat sources in the core elements of the structure under conditions of non-stationary thermal conductivity. [ABSTRACT FROM AUTHOR]

The main goal of the article is the development of the concepts of a reliable, safe, environmentally acceptable source that allows us to provide mankind with energy in the long term. The article uses computational and optimization procedures and research methods. Based on the concept of a lead-cooled natural safety fast reactor for power generation, a concept of a high-power reactor with innovative core materials is proposed. Based on the existing tokamak-type fusion reactor, a concept of a hybrid fusion-fission reactor is proposed for the disposal of long-lived radioactive waste from nuclear power. The minor actinides (237Np, 241Am, and 243Am) are used as blanket neutron breeders. Several of these hybrid reactors will be able to meet the needs of Russia's large-scale nuclear power industry in the middle of the 21st century in waste disposal. The proposed variants of the concepts of nuclear and hybrid reactors are characterized by internal safety. A nuclear reactor is resistant to all potential accidents. The hybrid reactor blanket is always in a subcritical state. The rate of transmutation of minor actinides only in the outer blanket reaches 70...80 kg/(MW year). When using an external and internal blanket, the rate of waste transmutation is higher. [ABSTRACT FROM AUTHOR]

Compton camera is a radiation detector that uses the kinematics of Compton scattering to estimate the direction of the gamma-ray incident. Compton camera has been used in many applications such as astronomy, medical, nuclear industry, and security. High time resolution in a Compton camera is essential to distinguish the incoming event in the detector. In this work, we developed a Compton camera using a fast decay scintillator and a high time resolution front end circuit to get a high-performance detector. The detector used an 8×8 multi-pixel photon counter (MPPC) array, which individually couple with a 2.5×2.5×5 mm3 GFAG (Gadolinium Fine Aluminum Gallate) scintillator. For processing the analog signal from the MPPC scintillators, the 64 channel ASIC (Application-Specific Integrated Circuit) is used. Each channel in the ASIC circuit consists of a pre-amplifier, shaper, monostable multivibrator, and slew-rate time over threshold. The ASIC will provide the digital output signal that contains the timing and energy information. The high-time resolution data acquisition circuit (PETnet) based on FPGA is used to acquire energy and time data from ASIC. [ABSTRACT FROM AUTHOR]

Modern industry creates new challenges in the field of materials science. In particular, the operating conditions for metal products are becoming tougher: critical units, pipelines, etc. - in the chemical industry and nuclear power. So, for example, the problem of finding and improving structural materials for working in molten salts of increased corrosive activity: fluorides, chlorides, carbonates, etc., at elevated temperatures and pressures remains urgent. Today, the main class of materials used for these environments is the group of corrosion-resistant alloys based on the Ni-Cr-Mo system. These alloys are prone to ordering. Moreover, for temperatures of 150... 400 ℃, short-range order effects are generally characteristic, and for 550... 650 ℃ - long-range order. The latter require a significant holding time (more than 500 hours) at the indicated temperatures [1, 2]. The stability of the structure of corrosion-resistant alloys is one of the conditions for maintaining its properties complex of during operation. Nickel-chromium-molybdenum alloys, being aging, require studying the influence of various factors on the precipitation rate of the second phases. Nickel-chromium- molybdenum alloys, being aging, require studying the influence of various factors on the rate of precipitation of the second phases. In this work, an attempt has been made to assess the effect of short-range and long-range order on the kinetics of the precipitation of intermetallic compounds using the example of alloy C4. Electron microscopy has shown the difference in the fraction of intermetallic precipitates in the region of minimum resistance to decomposition of a supersaturated solid solution in alloy C4 depending on the preformed short-range or long-range order. [ABSTRACT FROM AUTHOR]

Determination of Neodymium (Nd) recovery in fuel element plate (PEB) U3Si2/Al solution using cation exchange and precipitation methods was carried out. In the nuclear industry, the Nd isotope was one of the fission products of uranium-based fuels, in this case U3Si2/Al, which was used as a burn-up indicator because it was a stable element. As an indicator of burn up, Nd needs to be separated from other fission products such as cesium (Cs), uranium (U), Zirconium (Zr) to obtain pure Nd. Therefore, it was necessary to separate Nd using methods that had been used for the separation of other isotopes. By using established separation method, it was expected that the optimum recovery Nd would be obtained. Previous researchers have developed a method of cesium separation as a burn-up indicator, there were ion exchange and deposition methods. The recovery of Cs using the two methods were >95%. By obtaining a large recovery value, it was possible that this method could be used separate Nd in fuel element. This study aims to obtain recovery Nd using these two methods. The cation exchange process was carried out using 1000 mg of zeolite. PEB mixed solution containing Cs, Nd, other fission products and HCl 2 mL were added to the zeolite. The solution was shaken for 1 hour and then left for 24 hours. The solid phase and the liquid phase would form after 24 hours. The Nd element that were supposed to be in liquid phase. The Nd content were analyzed using X-Ray Fluorescence (XRF). Separation of Nd from PEB using the precipitation method was carried out by added 4 mL HClO4 and cooled at 0°C using an ice bath for 1 hour. A precipitate was formed after cooling for 1 hour. The liquid phase was separated from the solid phase. The Nd elements that were supposed to be in the liquid phase were analyzed using XRF. The analysis of Nd content using the two methods were used to calculate the Nd recovery. The recovery of Nd separation was 69.91% using the cation exchange method and 75.77% using deposition method, so the Nd separation using the precipitation method was better than separation using the cation exchange method. [ABSTRACT FROM AUTHOR]

Internal and external industry outlook techniques can be used to identify core organizational competencies and external threats. There is not much work done in the nuclear industry sector that focuses on qualitative and quantitative analysis to identify the industry’s core competence and external threats, especially at a local industry level. In this study, an internal analysis was performed using a quantitative approach as a first step followed by a qualitative approach was used to capture the general public’s knowledge of the sector in the United States. Internal data from a local nuclear plant was used for internal analysis while a questionnaire was used to study public understanding or perception. Based on initial findings, it is asserted that the general public’s knowledge is very low on the advantages of nuclear power, and the perception of nuclear safety is highly negative. Moreover, internal, and external factors are synthesized that signified the strength, weakness, opportunity, and threat (SWOT) of the sector. [ABSTRACT FROM AUTHOR]

As part of an independent assessment of the preoperational radiation environment around the Ostrovets nuclear power plant in Belarus, grass and foodstuffs were collected in 2019 for 14C analysis. The preoperational 14C specific activities in the Ostrovets region were shown to be similar to that of European data from other uncontaminated sites. [ABSTRACT FROM AUTHOR]

Mechanical systems degrade over time and ultimately fail. Failed components of the system are either replaced or repaired, non-repairable components are usually inexpensive, and it is often more cost-effective to replace. This paper examines the behavior of two component repairable systems. The main objective is to determine the system’s performance of three configurations with identical components; namely series, parallel, and cold standby. Closed form analytical expressions for steady state availability are derived and their behavior is illustrated by an example. [ABSTRACT FROM AUTHOR]

Neutron-induced reaction measurements, e.g. cross-sections and particle emission yields, require samples, called "targets", with specific properties depending on the reaction being studied and the quantities being measured. The target characteristics influence the results of these measurements and can have a strong impact on the total uncertainty of neutron-induced reaction data, which are important for industry and in research. This paper gives an overview of the main techniques applied in the target preparation laboratory at JRC-Geel for production and characterization of targets for neutron-induced reaction data measurements. The use of different targets is demonstrated with a few examples of total and reaction cross-section as well as nuclear fission experiments. In addition, on-going investigations and technical developments are presented. [ABSTRACT FROM AUTHOR]

The aim of the work is to create methodological provisions to justify the safe parameters of the thermal regime in permafrost rocks during the construction of underground complexes of small power nuclear plants in the Arctic region. The idea of the study is to assess the thermal regime of long-span mining excavations using mathematical modeling methods. To ensure the stability of underground mine excavations at the construction stage in the permafrost, the authors verify the use of various heat-protective systems. As the main stabilizing measures, heat insulation, artificial cooling and freezing of rocks can be noted. Separate results of experimental studies of increasing the stability of mine excavations in the permafrost zone at low positive temperatures are presented. The paper considers problems of determining the parameters of the temperature field around the excavations of an underground complex of various cross sections at the construction stage. Mathematical models of heat transfer in frozen rocks have been developed. The equation of energy transfer in a porous medium includes energy transfer by conduction and convection methods in proportion to the content of solid and liquid parts in the medium in accordance with the porosity of the medium. Modeling of thermal processes in rocks as porous media filled with water with a phase transition allowed the authors to create virtual computing stands where it is possible to work out thermal conditions during the construction of mine excavations of various sections under permafrost conditions.An analysis of the results of a series of computational experiments made it possible to justify the time factor during which it becomes possible to carry out construction mining of underground complexes without the use of special measures to cool rocks and prevent their defrosting. [ABSTRACT FROM AUTHOR]

Copyright of Conference Proceedings of the Société d'Ergonomie de Langue Française (SELF) is the property of Societe d'Ergonomie de Langue Francaise and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

The seismic qualification for the structural strength it is an issue for the assessment of the seismic safety of the Nuclear Power Plants. The qualification for seismic events in nuclear industry [4] includes the assessment of the structural integrity and fitness for operability during and after an earthquake. Such qualifications are done for various safety and non-safety equipment among which the pressure vessels are of a paramount importance. The seismic qualification is done either directly on prototypes or scaled prototypes (mock ups) or via analytical methods like analysis with finite elements. In any case the model should accurately represent the actual performance of the component or structure when it is subjected to the prescribed effects. The goal of this article is to underline the procedure to be followed for nuclear industry horizontal pressure vessels in order to obtain sound and credible results for equipment seismic qualification by using the unique analysis features of ANSYS 19. A seismic qualification analysis is carried out for the horizontal pressure vessel. The seismic event is overloading the anchoring system beyond the ultimate strength of the material. The zone where these big stresses fields are calculated is at the anchors level. The vessel as designed failed to be qualified for the seism excitations imposed to the model. In order to have the vessel qualified the anchoring way should be redesigned. By comparing the overall calculated equivalent stresses with the tensile yield strength we may pull the conclusion that the original structure design will fail. Instead the new redesigned anchoring system with 8 extra-anchors will stand. [ABSTRACT FROM AUTHOR]

This contribution deals with development of a system consisting of a base material and a composite laser clad with high corrosion resistance. The cladding material for laser overlaying was a powder mixture of inorganic substances based on copper and oxides of silicon, iron, calcium and magnesium. Experiments were carried out with three types of powder mixtures with different copper-inorganic oxides ratios. The disk laser Trumpf TruDisk 8002 with wavelength λ=1030 nm was used for producing three laser clad specimens whose total area was 60×95 mm. The substrate was C45 steel. It was 20 mm in thickness and was ground on both sides. Structures of the composite clads were examined using light microscopy and scanning electron microscopy (SEM). Local chemical analysis of dendrites and interdendritic spaces was carried out using EDX in the SEM. The laser clads were found to possess very fine and unique microstructures. The corrosion resistance of the substrate-composite laser clads systems were assessed by means of an advanced electrochemical method of measuring the corrosion rate, which relied on potentiodynamic corrosion testing involving linear polarization. The corrosion resistance data was compared to results of conventional salt spray corrosion tests. [ABSTRACT FROM AUTHOR]

Experimental Power Reactor (RDE) is a power reactor with High Temperature Gas cooled Reactor (HTGR). The safety justification of the RDE design is that radiation safety can be guaranteed which guarantees the safety of radiation workers and the community around the RDE site. To ensure the safety of workers and the community and the justification that RDE design meets safety criteria, a study of the zoning of the radiation area in the reactor is needed. The assessment is done based on HTR-10 parameters that types and power are similar to RDE. The research was conducted using computer simulation methods using ORIGEN2.1 and MCNP computer programs. Based on the Regulation of BAPETEN No.4 of 2013, concerning "Protection and Safety of Radiation in the Use of Nuclear Power", article 26 of the Work Area is divided into 2 namely Control areas and Supervision area. The zoning of the work area for radiation workers is determined based on the dosage amount calculated from the calculation of radiation sources, doses and radiation shields designed. The division of work area is determined based on the layout of the reactor building which is designed based on the RDE concept design. Based on the RDE concept design, the reactor building is divided into 4 levels, namely: 1). -12.70 m level; 2). Level ± 0.00 m; 3). Level + 12.70 m; and 4). Level +25.40 m. The results of the radiation dose calculation in RDE and the layout of the RDE design are used to determine the zoning area for radiation workers at each level area. Zoning is estimated in accordance with the rules of the BAPETEN regulatory body. Actions that must be taken for each zoning are also carried out. [ABSTRACT FROM AUTHOR]

The article describes a hypothetically possible organization of a Martian colony envisaging its employment in extraction and primary processing of the Solar system resources, which later could be delivered to the terrestrial market. Nuclear industry is considered to be the basis of the colony industry and the source of its revenue ensuring the colony self-sufficiency. Conditions in Mars are optimal in this regard from the environmental point of view and provide an opportunity to create an industry built on the basis of nuclear energy to build transport spaceships for delivering the mentioned above resources to the Earth. The article identifies main sources of resources to ensure the colony life, describes the principle of operation of the most important systems and production cycles, as well as of the life support and energy supply systems. Possibility of the colonists’ arrangement in lava pipes, diagram and description of residential, working and technical premises, as well as project implementation taking into consideration modern technologies are presented. [ABSTRACT FROM AUTHOR]

MAX phase ceramics are an important class of novel three-dimensional crystalline nanocomposites with an interesting combination of metal and ceramic-like properties that have made these materials highly regarded candidates for numerous technological applications, including in extreme environmental conditions. Some tests have also shown that the MAX phases may exhibit an extraordinary radiation resistance, which could be attractive for application in the nuclear industry. In this contribution, titanium tin carbide was inspected. The Ti2SnC phase was synthesized as a thin film by low-energy ion beam sputtering and subsequent thermal annealing, and it was irradiated by high-fluence low-energy Ar ions to inspect its radiation tolerance. The experiment showed that by the 2-step method of ion beam sputtering with thermal annealing thin films (several tens of nm) of the Ti2SnC phase can be successfully fabricated. The bombardment with high fluence heavy ions results in modification of the composite microstructure, but it has only a limited impact on the crystallinity of Ti2SnC grains. [ABSTRACT FROM AUTHOR]