Future Nuclear Power Research Articles

Facile and efficient sequestration of uranium using biomass from Saudi Arabia’s local date palms waste

Kingdom of Saudi Arabia has announced to utilize its domestic resources to enhance its future nuclear power capacity to a total of 17.6 GW by 2040. This ambitious plan is followed by mining and extraction of uranium from various approaches both physically and chemically. Therefore, an economical and efficient approach was devised for harvesting uranium content from aqueous solutions by using two bio-sorbent, i.e., date pit sawdust (DPS) and date palm biowaste (PDB). The DPS and PDB were analyzed with BET surface area, FT-IR, SEM, EDX, pHPZC and XRD techniques to examine the surface area, porosity, functional group on surface, morphology, point of zero charge of the materials and nature of materials respectively. Effect of parameters like sorbent dose, solutions pH, concentrations and time of contact on adsorption were studied in a batch method. The findings indicated that both DPS and PDB exhibited significant sequestration of U(VI) with maximum adsorption observed at 6 pH. However, PDB exhibited the maximum sorption percentage (78.80 %) and capacity (3.25 mg/g), followed by DPS (70.5 %, 2.47 mg/g, respectively), for uranium sequestration.

New developments of hydrogen impurity online-monitoring in liquid lithium of IFMIF-DONES

On the way to future nuclear fusion power plants, the International Fusion Materials Irradiation Facility (IFMIF) – DEMO Oriented Neutron Source (DONES), is an important key element between ITER and DEMO to study before the influence of DEMO-neutron irradiation on foreseen fusion materials. The core of DONES, currently under construction near Granada, Spain, is based on a circuit containing liquid lithium at elevated temperatures acting as a functional material for the (d,n)-Li reaction in a materials test cell. In addition to this actual function of DONES, there are important aspects of maintenance in which hydrogen isotopes are generated under operating conditions and dissolved in this aggressive and very reactive alkali metal. This implies strong unfavourable effects on the applied structural materials, e.g. hydrogen embrittlement and others.To counteract these unfavourable effects, endangering the safe operation, an Impurity Control System (ICS) is an integral part of the DONES instrumentation. As part of the tasks of the European Neutron Source (ENS) to develop redundant systems for monitoring impurities, a special sub-task was defined for the development of an electrochemical H-sensor for concentrations in liquid lithium, ECHSLL. It is determined by detecting the electrical potentials of the lithium melts compared to a standard Li-based chemical reference system. This allows an inherent material property to be directly correlated (i.e. through appropriate electrochemical instrumentation) with chemical concentration values. This article presents important advancements in the applied ECHSLL technique, such as improving laboratory measurements from stagnant conditions to dynamic and realistic flow conditions of the liquid lithium material, as well as appropriate approaches to overcome the challenges in distinguishing the hydrogen isotopes by ECHSLL system (protium and deuterium among given laboratory conditions).

Scaling in nuclear thermal hydraulics: Advances, applications and future perspectives in Spain

The demonstration of the safety, high performance and reliability of any man-made device relies heavily in experimental programs. For nuclear reactor safety demonstration, several experimental facilities are used for both testing the design and the validation of computational codes. In the field of thermal hydraulics, most experimental facilities are built at a smaller scale, thus the scaling analysis is a requirement in the licensing process of the nuclear power plant. This includes the analysis of the scaling capabilities of the computer codes, the scale and design differences with the licensed reactor and the methodologies applied for licensing.In collaboration with the Spanish regulatory Body, several Spanish university groups have contributed considerably to the development and application of scaling methodologies. This article provides an overview of the most relevant contributions presented in the last decades. The activities deal mainly with the use of system codes in scaling analysis. Specifically the works can be classified in the use of Kv scaling analyses, analysis of counterpart experiments, plant application and the scaling of uncertainties. Finally, the future challenges that will be addressed in relation to scaling are highlighted with emphasis to the contribution to the safe operation of current and future nuclear power plants.

Analysis of radwaste accumulation in various scenarios of NP development

Within the framework of “Proryv” project a radiation-equivalent approach to radioactive waste management is being envisioned with U and Pu recycling and MA transmutation. Successful industry-wide implementation of the design approaches should be planned in order to avoid considerable financial and radiological encumbrances caused by the NFC final stage for two-component nuclear power system (NPS) under formation on the basis of thermal and fast reactors. In order to ensure a successful industry-wide implementation of the approaches being developed, the back-end of the NFC should not constitute considerable a financial and radiological burden for the emerging two-component nuclear power system (NPS). This article addresses the problems concerning justification of radiological and technical-and-economic feasibility of MA partitioning and subsequent transmutation in FNR. The extent of MA accumulation as a result of TNR SNF reprocessing confirms the need for the introduction of MA partitioning technologies not only at all reprocessing plants planned for commissioning, but also at the plants now in operation. Based on available data, the study has shown that the implementation of the closed NFC with FNR contributes to significant reduction in the cost of disposal of radwaste compared to the scenario based exclusively on the development of VVER and open fuel cycle technologies. Recycling plutonium in fast reactors should be implemented in conjunction with MA to address environmental, non-proliferation and economic concerns of the back-end of advanced NFC. Within the scale of the future nuclear power system in Russia, an option such as this can only be realized on the basis of developing a FNR fleet.

Transient simulation and analysis of a supercritical CO2 heat removal system under different abnormal operation conditions

The supercritical carbon dioxide (sCO2) heat removal system, which is based on multiple closed Brayton cycles with sCO2 as the working fluid, is an innovative, self-propelling and modular heat removal system for existing and future nuclear power plants. Previous studies analysed its design, layout, control and operation. In addition, this study considers different sudden failures during the accident progress, e.g. failure of single sCO2 cycles, control systems and valves. These abnormal conditions were investigated with the thermal-hydraulic system code ATHLET for a generic Konvoi pressurized water reactor. In most cases, the failure of a single sCO2 cycle can be compensated. On the one hand, failure of the fans of the gas cooler leads to a pressure increase which may be mitigated by an inventory control system or cycle shutdown. On the other hand, unintended fan speed-up can cause compressor surge without adequate countermeasures. Furthermore, the system can operate under the cyclic blow-off from the steam generator safety valves when the relief valves are not available. Finally, the unintended closure of the valve which controls the steam flow through the compact heat exchanger triggers a fast cycle shutdown but a subsequent restart might be possible.

Development of a Decommissioning Robot with a Simple Structure Capable of Traversing Steps Using Two Different Drive Systems

In response to the imperative need for robotic involvement in the decommissioning of the Fukushima Daiichi Nuclear Power Plant, a proactive initiative was undertaken. This initiative led to the organization of the “7th Decommissioning Creative Robot Contest,” in which pivotal challenges related to nuclear plant decommissioning were addressed. Recognizing inaccessible areas within a decommissioned plant, the primary objective of this study was to develop a remotely operated robot capable of executing decontamination tasks in such environments. Two distinct locomotion systems were designed: mecanum wheels and crawlers. The mecanum wheels, characterized by their ability to execute approximately 100 mm vertical movements, facilitated the robot to surmount obstacles, particularly by negotiating 100 mm steps by engaging the tracks. Simultaneously, to address decontamination tasks at elevated locations, a threefold expandable ladder truck system was integrated, augmenting the operational range of the robot. Participation in the contest provided a platform for showcasing the developed technologies and validating their practicality. Despite encountering challenges during competition, such as damage to one locomotion system, the other locomotion system can be used to reach the destination. Experience serves as a crucial means of verifying technological advancements. Issues such as malfunctions in the range of motion control due to faulty limit switch contacts and unexpected loads on the tire elevation motors were noted, which hindered the achievement of the anticipated results. Despite these drawbacks, the adopted structural design demonstrates notable advantages, particularly in terms of maneuverability. The combination of mecanum wheels and crawlers along with a ladder truck system demonstrated adaptability to various scenarios. This adaptability holds significant promise for future nuclear power plant decontamination applications. While the competition may not have yielded the desired outcome, the lessons learned and the verified practicality of the developed technologies reinforce their potential utility in addressing the future challenges of nuclear plant decommissioning.

Development of a Diffusion Bonding Route for Joining Oxide-Dispersion-Strengthened (ODS) Steels for Nuclear Applications

Oxide-dispersion-strengthened (ODS) steels are candidate materials for components in current and future nuclear power plants. One of the issues with using ODS steels is the difficulty of joining them without loss of mechanical performance. In this study, austenitic ODS 316L stainless steel was diffusion-bonded to Inconel 718 superalloy. Having optimized the bonding conditions, a number of samples were made at 1200 °C with a bonding time of 1 hour and pressure of 10 MPa. Preliminary mechanical and microstructural analyses indicated the formation of a sound joint interface, despite slight grain growth in the ODS 316L. A post-bonding thermo-mechanical treatment (TMT) was conducted to refine and restore the microstructure of the ODS 316L. Comparative TEM investigations of the parent ODS alloy and the bonded samples (with and without TMT) along with statistical analyses showed that the Y–Ti–O oxide size distribution remains unaffected by the bonding and complementary TMT cycles, indicating stability of such particles even at very high temperatures and suitability of the devised route for joining the ODS 316L steel.

ON RADON ACTIVITY OF TECTONIC FAULTS IN THE AREA OF SITING THE SINOP NPP IN THE REPUBLIC OF TŰRKIYE

Problem statement. The paper provides an additional expanded justification for applying an innovative methodology in the area of the future Sinop NPP, planned to be deployed in the Republic of Tűrkiye, to identify the activity rate of tectonic faults in soil foundation based on comprehensive radon measurements using the PSACEA universal estimation scale. The purpose of the article. Current radon activity assessment of existing tectonic faults in Earth’s crust based on archival measurements of soil radon carried out earlier in Sinop Province. Conclusions and results. Current analysis of radon measurement results obtained previously by the track method made it possible to further assess the radon activity rate of tectonic faults existing in the area of the future nuclear power plant. The proposed methodology to assess radon activity of tectonic faults in Earth’s crust involves increasing safety during the construction and operation of the future nuclear power plant. The regulation on using this methodology as part of the subsurface monitoring at the Sinop NPP can be enshrined in job descriptions. This methodology can also be used as part of the seismic monitoring of other sites at the nuclear power plant, especially those located in high seismic risk zones.

Navigating the Regulatory Challenges and Economic Viability of Small Modular Nuclear Reactors: A Key to Future Nuclear Power Generation in the USA and Beyond

As the world grapples with the dual challenge of meeting growing energy demands and addressing climate change, small modular nuclear reactors (SMRs) have emerged as a promising solution. SMRs offer the potential for safe, reliable, and scalable nuclear power generation. This article delves into the regulatory hurdles and economic considerations that must be navigated to realize the full potential of SMRs in the United States and worldwide. By examining these challenges, we can better understand how SMRs can contribute to a sustainable and clean energy future

The rise of the Argentine Nuclear Program and the thwarted dream of industrialization (1950-1984)

The rise of the Nuclear Program in Argentina took place during the second stage of the process of Import Substitution Industrialization, which encourage local industry and the development of metalworking and electronics. In this context, one of the central aims of the National Atomic Energy Commission (CNEA) was to improve the domestic industry of goods and services in order to supply future nuclear power plants and promote technological autonomy. However, this philosophy began to struggle with the neoliberal reforms that were implemented after 1976. The primary objective of this work is to draw and analyze the main strategies implemented by CNEA to promote local industry. In this sense, this paper will be focus in the creation of the Metallurgy Department (1955), the Technical Assistance Service to Industry (1962), the National Industry Group (1965) and the creation of an Industrial Architect, ENACE SA (1980).

Forecast of clean energy generation in China based on new information priority nonlinear grey Bernoulli model.

The forecast of clean energy power generation is of major prominence to energy structure adjustment and the realization of sustainable economic development in China. In order to scientifically predict clean energy power generation data, a structure-adaptive nonlinear grey Bernoulli model submitted to the new information priority criterion (abbreviated as IANGBM) is established. Firstly, an improved conformable fractional accumulation operator that conforms to the priority of new information is proposed, which can effectively extract the information from small samples. Then, IANGBM is derived from the Bernoulli differential equation, and the perturbation bound theory proves that this model is suitable for the analysis of small sample data. In addition, the grey wolf optimization algorithm is utilized to optimize the model parameters to make the model more adaptable and generalized. To verify the superiority of the model, two cases consisting of wind and nuclear power generation prediction are implemented by comparing eight benchmark models involving IANGBM, GM, FGM, FANGBM, LR, SVM, BPNN, and LSTM. The experiment results demonstrate that the proposed model achieves higher prediction accuracy compared to the other seven competing models. Finally, the future nuclear and wind power generation from 2023 to 2030 are predicted by adopting the IANGBM(1,1) model. For the next 8 years, nuclear power generation will maintain stable development, while wind energy power generation will grow rapidly.

Preliminary study of the sub-medium São Francisco region overlooking the installation of future Brazilian nuclear power plants

Preliminary studies of site selection for the installation of nuclear plants in the northeast of Brazil have shown that the São Francisco river basin is a possible region for the implementation of these plants. For their operation, however, nuclear power plants require a reliable source of water for the cooling of heat rejected from the condenser that is sufficient for normal operation, shutdown, postulated accident conditions, and fire protection. The objective of this paper is to discuss safety issues and environmental impacts arising from the placement of nuclear power plants at the São Francisco river basin. The approach taken considered water availability throughout the year, the maintenance of thermal balance and climate changes. The present discussion indicates the necessity of a long-term management plan for the various uses of the São Francisco basin. An economic and social approach to the impacts of nuclear power plant operation and other agricultural and industrial activities in the region is also necessary. Finally, the study suggests the adoption of a variable-cycle cooling system, which will enable operation in all types of hydrological conditions expected in the São Francisco basin.

Experimental study on the flow characteristics of 7-pin hexagonal bundle assembly with grid spacers

Lead-cooled Fast Reactors (LFRs) are of great significance for future nuclear power systems. With the advantages of great neutronic properties and high passive safety, LFR has been selected as the reactor of China initiative Accelerator Driven System (CiADS), which has the potential to transmute long-lived nuclear waste into short-lived ones and enhance the utilization of nuclear fuel. The hexagonal bundle with grid spacers has been identified as a promising design of the CiADS fuel assembly. The new design of grid spacers has the advantages of reliable fixation, small flow resistance, and not easy to cause blockage. Flow characteristics in this fuel assembly model were revealed by the particle image velocimetry (PIV) method. The results showed the presence of cross-flow and high axial velocity areas around the grid spacers. The strongest cross-flow mixing was observed downstream of the grid spacers at a distance of approximately z/Dh = 7.5 (axial height/hydraulic diameter). Although the influence of the grid spacers was weak, it was still detectable downstream at a distance of z/Dh = 32. The axial velocity loss rates were obtained and they increased with Reynolds number. The highest axial velocity loss rate was in the edge subchannel. Measurements of axial pressure drop uncovered the pressure loss characteristics of grid spacers and a new correlation was proposed. This work contributes to the understanding of the flow and pressure drop characteristics of the CiADS fuel assembly and can facilitate the design of more efficient nuclear reactors.

The Future of Nuclear Power: A Philippine Perspective

A global transition toward sustainable energy systems is of capital importance to avert the adverse effects of climate change. However, at the forefront of this paradigm shift remains energy security as a key constituent. The Philippines, amid imposing high electricity rates because of the importation of coal and fossil fuels, continuously struggles with its energy consumption. As it commits to a 75% reduction and avoidance of greenhouse gas (GHG) emissions by 2030, the Philippines endeavors steps toward meeting its concomitant energy demand while investing in more sustainable energy sources. Among the most viable options, nuclear energy is integral in providing a zero-emission clean energy source to address the demand while attaining the country’s commitment to GHG reduction. Thus, national policy discussions on the introduction of nuclear power in the energy mix are of principal interest as its inclusion is projected to present colossal potential and prospects for the government and its people in terms of employment, energy security, and a sustainable environment. In lieu, this paper pivots on the future of nuclear power in the Philippine context through a comprehensive review of the status of its energy sector, the historical context and status of its nuclear power, public acceptance, capacity building, and economic feasibility.

Multimodel generalized predictive control of a heat-pipe reactor coupled with an open-air Brayton cycle

The heat-pipe reactor is based on the design concept of a solid-state reactor, and has gradually become a preferred reactor type for future space nuclear power and new nuclear power technology applications. However, due to the all-solid-state assembly mode, dynamic and control characteristics of the heat-pipe reactor are different from those of traditional reactors. In this regard, the paper proposed a multimodel generalized predictive control (MMGPC) method for a heat-pipe reactor coupled with an open-air Brayton cycle. First, based on the dynamic characteristics, the control strategy of the heat-pipe reactor system was formulated. Then, decoupling controllers and generalized predictive controllers of the reactor power and rotating shaft speed were designed under the control strategy, and all the dependent models in the controllers were established with the multimodel modeling principle to construct the MMGPC system. Finally, to verify the performance of the control system, step load-change transients of the heat-pipe reactor system were simulated. The results demonstrates that the MMGPC method is applicable to and has excellent control performances for the heat-pipe reactor coupled with an open-air Brayton cycle.

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

The review starts by highlighting the significance of nuclear power plants in the contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions. Then, it describes the impact of irradiation on the microstructure and mechanical properties of reactor structural materials. The main part provides the reader with a thorough overview of crystal plasticity models developed to address the irradiation effects so far. All three groups of the most important materials are included. Namely, the Zr alloys used for fuel cladding, austenitic stainless steels used for reactor internals, and ferritic steels used for reactor pressure vessels. Other materials, especially those considered for construction of future fission and fusion nuclear power plants, are also mentioned. The review also pays special attention to ion implantation and instrumented nanoindentation which are common ways to substitute costly and time-consuming neutron irradiation campaigns.

Selective removal of uranyl ions using ion-imprinted amino-phenolic functionalized chitosan

The recovery of uranium from aqueous effluents is very important for both the environment and the future of nuclear power. However, issues of sluggish rates and poor selectivity persist in achieving high-efficiency uranium extraction. In this study, uranyl (UO22+) ions were imprinted on an amino-phenolic chitosan derivative using an ion-imprinting method. First, 3-hydroxy-4-nitrobenzoic acid (HNB) units were joined to chitosan via amide bonding, followed by reducing the -NO2 residues into -NH2. The amino-phenolic chitosan polymer ligand (APCS) was coordinated with UO22+ ions, then cross-linked with epichlorohydrin (ECH), and finally the UO22+ ions were taken away. When compared to non-imprinted sorbent, the resulting UO22+ imprinted sorbent material (U-APCS) recognized the target ions preferentially, allowing for much higher adsorption capacities (qm = 309 ± 1 mg/g) and improved adsorption selectivity for UO22+. The FTIR and XPS analyses supported the pseudo-second-order model's suggestion that chemisorption or coordination is the primary adsorption mechanism by fitting the data well in terms of kinetics. Also, the Langmuir model adequately explained the isotherms, suggesting UO22+ adsorption in the form of monolayers. The pHZPC value was estimated at around 5.7; thus, the optimum uptake pH was achieved between pHs 5 and 6. The thermodynamic properties support the endothermic and spontaneous nature of UO22+ adsorption.

Numerical Simulation and Experimental Study on Gas Flow in an Open Lattice Structure for an Advanced Space Nuclear Power System

Helium flow in the rod bundle channel with an open lattice structure is an important phenomenon for the advanced gas-cooled nuclear core design. In this study, thermal analysis with helium flow in various channel designs is conducted based on CFD methods to determine a dimension-optimized rod bundle channel. An experimental study then follows in order to pick up an appropriate gas flow model in further numerical simulation. Finally, helium flow in the bundle channels consisting of 217 rods is simulated using this chosen flow model, which shows to satisfy the requirements of basic thermal analysis of a newly designed gas-cooled reactor with an open lattice structure. Generally, this work will contribute to the design and analysis of the future advanced space nuclear power system.

Enhanced fatigue property by fabricating a gradient nanostructured surface layer in a reduced-activation steel

Reduced activation ferritic/martensitic (RAFM) steels have been selected as candidate structural materials for future advanced nuclear power systems. In the present work, the influence of a gradient nanograined surface layer on the fatigue properties of RAFM steels was studied. A gradient nanostructured (GNS) surface layer with a thickness of ∼85 ​μm was prepared on RAFM steel utilizing surface mechanical rolling treatment (SMRT). The mean grain size was approximate 43 ​nm at the topmost surface and increased gradually with depth. The results of the stress-controlled tension-compression fatigue experiments showed that the fatigue life enhanced approximately 6 times in the SMRT samples compared to the corresponding base metal counterparts. The relationship between the applied stress amplitude and the fatigue lifetime, and the fracture morphology showed that the surface strengthening and strain delocalization were caused by GNS, which suppressed surface crack initiation process, and hence the fatigue properties of RAFM steels improved. In addition, the deformation compatibility in GNS and coarse-grained boundaries leading to more dislocation interactions and accumulation during the cyclic process, also plays a crucial role in enhancing the fatigue properties of RAFM steel.

Nuclear Fuel Cycle Issues and Future of Nuclear Power

Nuclear Fuel Cycle Issues and Future of Nuclear Power