Editorial

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2 pages, 282 KiB

Open AccessEditorial

Nuclear and New Energy Technology

by Roman Davydov

Energies 2022, 15(16), 6046; https://doi.org/10.3390/en15166046 - 20 Aug 2022

Cited by 2 | Viewed by 1264

Abstract

Due to the growing demand for electrical energy generation worldwide [...] Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

Research

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20 pages, 7045 KiB

Open AccessArticle

Enhancing LOCA Breach Size Diagnosis with Fundamental Deep Learning Models and Optimized Dataset Construction

by Xingyu Xiao, Ben Qi, Jingang Liang, Jiejuan Tong, Qing Deng and Peng Chen

Energies 2024, 17(1), 159; https://doi.org/10.3390/en17010159 - 27 Dec 2023

Viewed by 776

Abstract

In nuclear power plants, the loss-of-coolant accident (LOCA) stands out as the most prevalent and consequential incident. Accurate breach size diagnosis is crucial for the mitigation of LOCAs, and identifying the cause of an accident can prevent catastrophic consequences. Traditional methods mostly focus [...] Read more.

In nuclear power plants, the loss-of-coolant accident (LOCA) stands out as the most prevalent and consequential incident. Accurate breach size diagnosis is crucial for the mitigation of LOCAs, and identifying the cause of an accident can prevent catastrophic consequences. Traditional methods mostly focus on combining model algorithms and utilize intricate composite model neural network architectures. However, it is crucial to investigate whether greater complexity necessarily leads to better performance. In addition, the consideration of the impact of dataset construction and data preprocessing on model performance is also needed for model building. This paper proposes a framework named DeepLOCA-Lattice to experiment with different preprocessing approaches to fundamental deep learning models for a comprehensive analysis of the diagnosis of LOCA breach size. The DeepLOCA-Lattice involves data preprocessing via the lattice algorithm and equal-interval partitioning and deep-learning-based models, including the multi-layer perceptron (MLP), recurrent neural networks (RNNs), convolutional neural networks (CNNs), and the transformer model in LOCA breach size diagnosis. After conducting rigorous ablation experiments, we have discovered that even rudimentary foundational models can achieve accuracy rates that exceed 90%. This is a significant improvement when compared to the previous models, which yield an accuracy rate of lower than 50%. The results interestingly demonstrate the superior performance and efficacy of the fundamental deep learning model, with an effective dataset construction approach. It elucidates the presence of a complex interplay among diagnostic scales, sliding window size, and sliding stride. Furthermore, our investigation reveals that the model attains its highest accuracy within the discussed range when utilizing a smaller sliding stride size and a longer sliding window length. This study could furnish valuable insights for constructing models for LOCA breach size estimation. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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17 pages, 4860 KiB

Open AccessArticle

Influence of Cooling Water Parameters on the Thermal Performance of the Secondary Circuit System of a Modular High-Temperature Gas-Cooled Reactor Nuclear Power Plant

by Xin Wang, Gang Zhao, Xinhe Qu, Xiaoyong Yang, Jie Wang and Peng Wang

Energies 2023, 16(18), 6560; https://doi.org/10.3390/en16186560 - 12 Sep 2023

Cited by 1 | Viewed by 931

Abstract

This study quantitatively analysed the influence of cooling water parameters on the performance of a modular high-temperature gas-cooled reactor (MHTGR) nuclear power plant (NPP). The secondary circuit system and cold-end system were modelled using EBSILON software, version 16.0. The influence of cooling water [...] Read more.

This study quantitatively analysed the influence of cooling water parameters on the performance of a modular high-temperature gas-cooled reactor (MHTGR) nuclear power plant (NPP). The secondary circuit system and cold-end system were modelled using EBSILON software, version 16.0. The influence of cooling water inlet temperature and mass flow rate on the thermal performance of the secondary circuit system was analysed over the full power range with the goal of optimising net power. Under 100% rated condition, for each 1 °C increase in cooling water inlet temperature between 10 and 33 °C, the net power and cycle efficiency decreased by 0.67 MW and 0.14%, respectively, whereas the heat consumption rate increased by 28.72 kJ/(kW·h). The optimal cooling water mass flow rates corresponding to cooling water inlet temperatures of 16 °C and 33 °C were obtained. The optimal cooling water mass flow rate decreased nonlinearly with decreasing power levels. At a cooling water inlet temperature of 33 °C, an increase in cooling water mass flow rate from the designed value (7697.61 kg/s) to the optimal value (10,922.14 kg/s) resulted in a 1.03 MW increase in net power. These findings provide guidelines for MHTGR NPP operation optimisation and economic improvement, especially under high-temperature weather conditions. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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18 pages, 7322 KiB

Open AccessArticle

Developing a Reactivity-Equivalent Physical Transformation to Simulate an Axially Heterogeneous Boiling Water Reactor

by Robert Mossop, Bruno Merk, Maulik Patel, Tetsushi Hino and Aiden Peakman

Energies 2023, 16(8), 3359; https://doi.org/10.3390/en16083359 - 11 Apr 2023

Viewed by 993

Abstract

Hitachi is advancing their designs for a conceptual reactor called the resource-renewable boiling water reactor (RBWR), a concept reactor similar to the advanced boiling water reactor with a harder neutron spectrum. This design aims to minimise construction costs and waste production as well [...] Read more.

Hitachi is advancing their designs for a conceptual reactor called the resource-renewable boiling water reactor (RBWR), a concept reactor similar to the advanced boiling water reactor with a harder neutron spectrum. This design aims to minimise construction costs and waste production as well as to utilise separated plutonium and minor actinide fuel. However, the axial heterogeneity of the design poses calculation difficulties. The aim of this work is to use a known method, reactivity-equivalent physical transformation (RPT), for calculating fuel with double heterogeneity and apply it to a BWR-type fuel pin. This could reduce the calculation time needed for optimisation of the design of the RBWR. The objective of the study is to use SCALE 6.2 to produce an equivalent axial pin model by comparison with the burnup and neutron spectra of a radial model of the fuel. This model can then be used for 2D burnup calculations, and in future work will be used for the generation of two-group and multigroup cross-sections for further deterministic calculations as part of a two-step approach for analysis of the RBWR. The RPT method has been extensively tested on spherical fuel, and SCALE is a standard industry code. The initial radial model is a hexagonal assembly with 20% enriched UO₂ fuel in a zircaloy cladding, surrounded by light water moderator. The derived axial model has a water density distribution taken from Hitachi’s RBWR designs. Criticality over 70 GWd/tU burnup is estimated using the model. The application of the RPT to the BWR pin was shown to be possible, but to have limitations with the introduction of additional radial complexity. For a single pin, excellent agreement between the radial and axial models could be found across a range of water densities, but in the case of an assembly level calculation distinct equivalence models were required for each water density. In addition, the produced RPT model is validated using SCALE’s 3D Monte Carlo module, KENO. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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16 pages, 4560 KiB

Open AccessArticle

iMAGINE—Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century

by Bruno Merk, Dzianis Litskevich, Anna Detkina, Omid Noori-kalkhoran, Lakshay Jain, Elfriede Derrer-Merk, Daliya Aflyatunova and Greg Cartland-Glover

Energies 2023, 16(7), 3120; https://doi.org/10.3390/en16073120 - 29 Mar 2023

Cited by 2 | Viewed by 1534

Abstract

Nuclear technologies have the potential to play a major role in the transition to a global net-zero society. Their primary advantage is the capability to deliver controllable 24/7 energy on demand. However, as a prerequisite for successful worldwide application, significant innovation will be [...] Read more.

Nuclear technologies have the potential to play a major role in the transition to a global net-zero society. Their primary advantage is the capability to deliver controllable 24/7 energy on demand. However, as a prerequisite for successful worldwide application, significant innovation will be required to create the nuclear systems of the 21st century, the need of the hour. The pros (low harmful emissions, high reliability, low operational expenses, and high energy density) and cons (environmental damage, fuel waste disposal concerns, limited uranium reserves, and long construction time-frame) of nuclear are discussed and analysed at different levels—the societal and public recognition and concerns (accidents, weapons, mining, and waste) as well as the scientific/engineering and economic level—to assure a demand-driven development. Based on the analysis of the different challenges, a vision for the nuclear system of the 21st century is synthesised consisting of three pillars—unlimited nuclear energy, zero waste nuclear, and accident-free nuclear. These three combined visions are then transformed into dedicated and verifiable missions that are discussed, in detail, regarding challenges and opportunities. In the following, a stepwise approach to the development of such a highly innovative nuclear system is described. Essential steps to assure active risk reduction and the delivery of quick progress are derived as answers to the critique on the currently observed extensive construction time and cost overruns on new nuclear plants. The 4-step process consisting of basic studies, experimental zero power reactor, small-scale demonstrator, and industrial demonstrator is described. The four steps, including sub-steps, deliver the pathway to a successful implementation of such a ground-breaking new nuclear system. The potential sub-steps are discussed with the view not only of the scientific development challenges but also as an approach to reduce the regulatory challenges of a novel nuclear technology. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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15 pages, 3637 KiB

Open AccessArticle

Photosensitivity of Nanostructured Schottky Barriers Based on GaP for Solar Energy Applications

by Vasily Rud, Doulbay Melebaev, Viktor Krasnoshchekov, Ilya Ilyin, Eugeny Terukov, Maksim Diuldin, Alexey Andreev, Maral Shamuhammedowa and Vadim Davydov

Energies 2023, 16(5), 2319; https://doi.org/10.3390/en16052319 - 28 Feb 2023

Cited by 3 | Viewed by 1276

Abstract

This work investigates the surface-barrier photoelectric properties of Au-palladium-n-GaP structures. Research into the visible spectrum region, under the action of both linearly polarized and natural radiation, provides us with new information about the height of the barrier, the interface m-s section, and the [...] Read more.

This work investigates the surface-barrier photoelectric properties of Au-palladium-n-GaP structures. Research into the visible spectrum region, under the action of both linearly polarized and natural radiation, provides us with new information about the height of the barrier, the interface m-s section, and the GaP band structure. SBs based on GaP (p- and n-type) are helpful for researchers in developing advantageous structures for creating various photovoltaic devices—photodetectors for fiber-optic control of energy systems or possible structures for solar energy. Despite many years of research, issues concerning the band structure of semiconductors based on the phenomenon of photoelectroactive absorption in such surface-barrier structures’ m-s remain urgent in the creation of new high-performance devices. Such structures may also be interesting for creating solar energy systems. They create a thin insulating dielectric layer (usually an oxide layer) in solar cells on SBs between the m and the semiconductor substrate. The advantage of solar cells based on m dielectric semiconductor structures is the strong electric field near the surface of the semiconductor that usually has a direction favoring the collection of carriers created by short-wavelength light. Diffusion of impurities usually results in crystal defects in the active region. There are no such defects in the studied elements. This is also the difference between solar cells on m dielectric structures and elements with diffusion in p-n junctions. We studied the PS of Au-Pd-n-GaP nanostructures to determine the height of the potential barrier qφ_Bo and obtained accurate data on the zone structure of the n-GaP. The PS of nanostructured Au-Pd-n-GaP structures was studied in the visible region of the spectrum. Essential information about the semiconductor’s potential barrier parameters and band structure was obtained. The intermediate Pd nanolayer between Au and GaP has specific effects on the Au-Pd-n-GaP nanostructure, which are of considerable practical and scientific significance for future needs. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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28 pages, 5301 KiB

Open AccessArticle

Phase-Homogeneous LiFePO₄ Powders with Crystallites Protected by Ferric-Graphite-Graphene Composite

by Dmitry Agafonov, Aleksandr Bobyl, Aleksandr Kamzin, Alexey Nashchekin, Evgeniy Ershenko, Arseniy Ushakov, Igor Kasatkin, Vladimir Levitskii, Mikhail Trenikhin and Evgeniy Terukov

Energies 2023, 16(3), 1551; https://doi.org/10.3390/en16031551 - 03 Feb 2023

Cited by 1 | Viewed by 1443

Abstract

Phase-homogeneous LiFePO₄ powders have been synthesized. The content of impurity crystalline phases was less than 0.1%, according to synchrotron diffractometry (SXRD) data. Anisotropic crystallite sizes

{\bar{L}}_{V [h k l]}

were determined by XRD. A low resistance covering layer of mechanically [...] Read more.

Phase-homogeneous LiFePO₄ powders have been synthesized. The content of impurity crystalline phases was less than 0.1%, according to synchrotron diffractometry (SXRD) data. Anisotropic crystallite sizes

{\bar{L}}_{V [h k l]}

were determined by XRD. A low resistance covering layer of mechanically strong ferric-graphite-graphene composite with impregnated ferric (Fe³⁺) particles < 10 nm in size increases the cycleability compared to industrial cathodes. In accordance with the corrosion model, the destruction of the Fe³⁺-containing protective layer of crystallites predominates at the first stage, and at the second stage Fe escapes into the electrolyte and to the anode. The crystallite size decreases due to amorphization that starts from the surface. The rate capability, Q(t), has been studied as a function of

{\bar{L}}_{V [h k l]}

, of the correlation coefficients

r_{i k}

between crystallite sizes, of the Li diffusion coefficient, D, and of the electrical relaxation time, τ_el. For the test cathode with a thickness of 8 μm, the values of D = 0.12 nm²/s, τ_el = 8 s were obtained. To predict the dependence Q(t), it is theoretically studied in ranges closest to experimental values: D = 0.5 ÷ 0.03 nm²/s, τ_el = 8/1 s, average sizes along [010]

{\bar{L}}_{1}

= 90/30 nm, averaged

\bar{r}

= 0/1. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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16 pages, 2535 KiB

Open AccessArticle

Online Multiphase Flow Measurement of Crude Oil Properties Using Nuclear (Proton) Magnetic Resonance Automated Measurement Complex for Energy Safety at Smart Oil Deposits

by Rustem Kashaev, Nguyen Duc Ahn, Valeriya Kozelkova, Oleg Kozelkov and Valentin Dudkin

Energies 2023, 16(3), 1080; https://doi.org/10.3390/en16031080 - 18 Jan 2023

Viewed by 1951

Abstract

The necessity of a flow express control of oil dispersed system (ODS) properties, such as crude oil, oil products, water–oil emulsions, and polluted waters, is substantiated. This control is necessary for the production and preparation of oil for transportation through the pipeline and [...] Read more.

The necessity of a flow express control of oil dispersed system (ODS) properties, such as crude oil, oil products, water–oil emulsions, and polluted waters, is substantiated. This control is necessary for the production and preparation of oil for transportation through the pipeline and oil refining, oil products, and wastewater treatment systems. A developed automatic measuring complex (AMC) is used to implement the concept of digital oil deposits. The primary measuring device is a relaxometer developed by us based on nuclear (proton) magnetic resonance (PMR). The design and operation algorithm of the AMC and the relaxometer are described. Equations have been developed to determine the ODS characteristics using the measured PMR parameters. This makes it possible to determine the flow rates of crude oil, the concentration of water in the oil, the concentration of asphaltene, resins, and paraffins in the oil, as well as the density, viscosity, and molecular weight of the oil. Additionally, it is possible to determine the dispersed distribution of water droplets in emulsions in oil production and treatment units. Data on this distribution will improve the management of separation processes. It has been established that the implemented control of multiphase ODS using PMR parameters (relaxation times, populations of proton phases, and amplitudes of spin-echo signals) makes it possible, using AMC, to assess the consumption of electricity in technological processes at the digital oil deposits, as well as during the transportation of oil and oil products through pipelines. AMC makes it possible to reduce electrical energy consumption in technological installations and reduce pollution emissions into wastewater. The advantages of using the developed AMC are shown in examples of its application. Such as an assessment of the influence of the gas factor on electricity consumption during oil transportation through pipelines or compensation for the additional moment of resistance on the shaft of the submersible motor, which is caused by surface tension forces at the interface of water droplets in the emulsion. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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16 pages, 3120 KiB

Open AccessArticle

New Optical System for Long Distance Control of Electrical Energy Flows

by Vadim Davydov, Bogdan Reznikov and Valentin Dudkin

Energies 2023, 16(3), 1040; https://doi.org/10.3390/en16031040 - 17 Jan 2023

Cited by 7 | Viewed by 989

Abstract

The problems that arise during the transmission of control commands for key elements and data on their execution via communication systems over long distances at energy facilities are considered. The necessity of a new approach to solving this problem using a fiber-optic communication [...] Read more.

The problems that arise during the transmission of control commands for key elements and data on their execution via communication systems over long distances at energy facilities are considered. The necessity of a new approach to solving this problem using a fiber-optic communication line (FOCL) is substantiated. A new design of analog FOCL has been developed for transmitting control commands for key elements of substations and switching data. A new method for forming an optical signal in a laser transmitting module using direct current modulation is proposed. The advantages of using a new method for generating commands for control signals and switching data using a sequence of command codes compared with digital signals currently used in control and monitoring systems are substantiated. The main parameters of the developed analog FOCL have been calculated. An experimental prototype of an analog FOCL was assembled, and research was conducted. The results of calculations and experimental data are compared. The directions for further modernization of the developed FOCL are determined to increase the distance for transmitting an optical signal up to 600 km without the use of servers, the maintenance of which in the power transmission line system in some cases is challenging, expensive, and not always possible. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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9 pages, 1092 KiB

Open AccessArticle

Simulation of Electromagnetic Implosion of Metal Shells to Obtain Supercritical Fluids

by Valery Antonov and Nicolay Kalinin

Energies 2022, 15(23), 8953; https://doi.org/10.3390/en15238953 - 26 Nov 2022

Viewed by 924

Abstract

This study analyzes the conditions for creating the energy density necessary to obtain supercritical fluids of substances with parameters (temperature T > 1 eV, density N > 1022 cm⁻³, specific energy density ε > 100 kJ/g). The calculations are carried out [...] Read more.

This study analyzes the conditions for creating the energy density necessary to obtain supercritical fluids of substances with parameters (temperature T > 1 eV, density N > 1022 cm⁻³, specific energy density ε > 100 kJ/g). The calculations are carried out on the basis of the one-dimensional (1D) two-temperature (2T) magneto hydrodynamic radiation model, which takes into account the physical processes occurring in the energy storage, switching system and the pulsed plasma load-a cylindrical compressible conductive shell. Developing a mathematical model, we assumed that physical processes were self-consistent. The simulation results were presented as time dependences of the main process parameters. Calculations showed that it becomes possible to sharpen the radiation pulse and pressure in the shock wave. As a result, we formulated the requirements for a laboratory energy source to establish the characteristics of a current pulse flowing through a conductive cylindrical shell and its dimensions (radius and thickness) necessary to achieve the goal. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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Review

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17 pages, 2169 KiB

Open AccessFeature PaperReview

Feasibility of Safe Operation of WWER-440-Type Nuclear Power Plants for Up to 60–70 Years

by Tamás János Katona, Ágnes Biro and Sándor Rátkai

Energies 2023, 16(10), 4170; https://doi.org/10.3390/en16104170 - 18 May 2023

Cited by 1 | Viewed by 1021

Abstract

Most WWER-440 reactors are operated over the planned operational lifetime of 30 years. Now, the owners/operators are preparing for the second phase of extending the operation. The paper presents an overview of the most important aspects of ageing of the main components of [...] Read more.

Most WWER-440 reactors are operated over the planned operational lifetime of 30 years. Now, the owners/operators are preparing for the second phase of extending the operation. The paper presents an overview of the most important aspects of ageing of the main components of the WWER-440-type reactors based on the operational and ageing management experiences and primary research efforts supporting the operation. The paper aims to demonstrate that the expectations for the operability of these reactors for up to 60–70 years are realistic. The scope of the review is limited to the ageing of the reactor pressure vessel, vessel internals, and steam generator, which are the lifetime-limiting components besides the containment structure. Some of the corrective actions, improvements of in-service inspections, maintenance, and ageing management are also considered in the paper. It is shown that the selection of materials and unavoidable material degradation processes do not limit the operation of the WWER-440 reactors for up to 60–70 years under the established operational environment and ageing management practice. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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12 pages, 703 KiB

Open AccessReview

Review of the Requirements for Load Following of Small Modular Reactors

by Choong-koo Chang and Harold Chisano Oyando

Energies 2022, 15(17), 6327; https://doi.org/10.3390/en15176327 - 30 Aug 2022

Cited by 4 | Viewed by 2127

Abstract

CO₂ net neutralization by 2050 is a global target. Renewable energy and nuclear power generation are emerging as major power sources for CO₂ net neutralization. Therefore, this paper comprehensively reviews the load-following operation method of nuclear power plants as a method [...] Read more.

CO₂ net neutralization by 2050 is a global target. Renewable energy and nuclear power generation are emerging as major power sources for CO₂ net neutralization. Therefore, this paper comprehensively reviews the load-following operation method of nuclear power plants as a method to compensate for intermittency, which is the biggest weakness of renewable energy. First, this paper looks at the types of SMRs and elaborates the concept and necessity of load following. The comprehensive requirements for the load-following operation of an SMR, i.e., planned operation, automatic generation control, governor-free operation, cooperative control of the reactor and turbine generator, unit control of a multiple-module SMR, cogeneration, etc., are studied. Finally, the interaction between an SMR and the power grid during load-following operation and other technical issues are also reviewed. This paper can be used as a guide for load-following operations or as a guide for requirement analysis when developing a comprehensive control system of load following in SMR fleets. Full article

(This article belongs to the Special Issue Nuclear and New Energy Technology)

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