Utilization Of Nuclear Energy Research Articles

Intrinsically morphological effect of perovskite BaTiO3 boosting piezocatalytic uranium extraction efficiency and mechanism investigation

Developing a convenient, efficient and eco-friendly approach for the recovery of U(VI) ion is a key measure to solve the environmental problems arising from the utilization of nuclear energy. Herein, the high efficiency of uranium extraction is realized by the piezo property of perovskite BaTiO3, revealing the intrinsically morphological engineering effect on the piezocatalytic performance. Especially, BaTiO3 nanowires (BTO NWs) exhibit not only an excellent piezocatalytic activity with U(VI) extraction rate of 96.8% in a UO2(NO3)2 aqueous solution compared to 71.3% of BaTiO3 nanoparticles (BTO NPs), but also a promising piezocatalyst for U extraction in a real U-mining wastewater with various pH ranges. Piezo response force microscopy and finite elemental simulation show that the piezo response of BTO NWs is much higher than BTO NPs. Additionally, some factors (pH, various ions, different powers) are explored on piezocatalytic efficiency for U(VI) extraction. The results from electron spin resonance and the charge/radical capture experiments confirm that the active species (e-, •O2-, •OH) stemmed from the piezo induction of BTO NWs and BTO NPs in the piezocatalytic U(VI) reduction process. The present work reveals the structure-performance correlation during piezocatalysis and highlights the crucial role of piezocatalysis in dealing with environmental problems.

Radial Basis Function Surrogate Model-Based Optimization of Small Light-Weight Lead-Bismuth Reactor Core

Owing to their high miniaturization potential and strong natural circulation capability, lead-bismuth reactors have been widely employed for nuclear energy utilization as well as military and civilian applications. However, there is a need to optimize the design of these reactors. To solve the complex high-dimensional nonlinear single-/multiobjective optimization problem of lead-bismuth reactors, we proposed a single-/multiobjective optimization method (termed as RBF-OLHS-NGA/NSGA II method) for optimizing the reactor core, which is based on the radial basis function (RBF) surrogate model (for prediction), orthogonal Latin hypercube sampling, niche genetic algorithm (for single-objective optimization), and nondominated sorting genetic algorithm (for multiobjective optimization). In view of this approach, the design optimization procedure of the lead-bismuth reactor based on RBF (DOPPLER-R) was developed, which combined the reactor Monte Carlo (RMC) code and the steady-state thermo-hydraulic analysis calculation (STAC) code to sample, predict, and optimize reactor core parameters. Furthermore, the single-/multiobjective optimization approach was verified by considering the core fuel loading and active zone volume of SPALLER-4 as the optimization objectives. The results show that the RBF surrogate model can accurately and rapidly predict the core characteristic parameters of lead-bismuth reactors. When compared to the value calculated using the RMC code, the relative error associated with the predicted effective multiplication factor ( <math xmlns="http://www.w3.org/1998/Math/MathML" id="M1"> <msub> <mrow> <mi>k</mi> </mrow> <mrow> <mi>e</mi> <mi>f</mi> <mi>f</mi> </mrow> </msub> </math> ) is within ±0.1%. Compared to the unoptimized values, the single-objective optimized fuel loading reduced by 400 kg, multiobjective optimized fuel loading decreased by 455–493 kg (optimization ratio of 78%–84%), and active zone volume reduced by 166362–182888 cm3 (optimization ratio of 72%–79%). These results prove that the proposed optimization method is feasible, exhibits high efficacy, and can provide new technical ideas for single-/multiobjective optimization of multiphysics, multivariable, and multiconstraint lead-bismuth reactors.

Analysis of the nuclear energy systems as an alternative propulsion system option on commercial marine vessels by utilizing the SWOT-AHP method

The utilization of alternative fuels such as LNG, methanol, hydrogen, ammonia, and nuclear energy on marine vessels is quite critical to cope with the challenging air pollution regulations set by IMO and to realize global de-carbonization strategies. Nuclear energy has come to the fore with high and sustainable energy density as well as a carbon-free feature among the other potential alternative maritime fuels. Nuclear energy has been used successfully for icebreakers, submarines, and naval vessels up to now and it has been researched for commercial ships, despite a few unsuccessful projects because nuclear energy brings certain difficulties during its utilization, especially in commercial ships. That’s why a SWOT analysis has been performed to determine all internal and external factors on the utilization of nuclear energy in commercial ships as a maritime fuel. The SWOT factors and sub-factors have been established with the aid of comparable energy studies in the literature and maritime sector reports. Twelve marine experts with an average of 12.8 years of experience have participated in a survey to determine the priority weight of each main and sub-factors. Opportunity and strength aspects have the highest weight with 0.362 and 0.302 respectively. On the other hand, threats have a substantial amount of weight with 0.212. Being eco-friendly, reducing dependency on fossil fuels, and preventing fuel fluctuations constitute the three most prominent features among the sub-factors. However, safety and security challenges, which are 4th place among the sub-factors, should be eliminated as much as possible for successful applications of nuclear energy. Experience gathered from past and existing nuclear-powered marine vessels will have been beneficial to overcome difficulties in the utilization of nuclear energy in commercialships.

Editorial: Assessment of nuclear and renewable energy utilization for sustainable economic growth

performance of predictions based on other machine learning models, econometric models and deep learning models for Bohai-Rim Steam-Coal Price Index on the horizon 5 January 2011 to 22 June 2022.Governments are responsible for the elaboration of the policies to achieve the transition towards environmentally-friendly and sustainable technologies. However, the effectiveness of these policies depends on the capacity of companies to use government subsidies to perform research and development (R&D). Government subsidies determined more patent outputs in 68 LiB Chinese companies in the period 2012-2018, but a significant growth in R&D has not been achieved (Wu et al., 2022). Managerial ability is directly correlated with company performance and might help firms to promote green technologies and renewable energy consumption to reduce pollution (Chen et al., 2023).

The constructions of the fully flexible s-triazine-based covalent organic frameworks for adsorping iodine and fluorescence sensing p-nitrophenol and iodine

The effective capture of radioactive vapor waste during fission is of great significance to the safe utilization of nuclear energy. Covalent organic frameworks (COFs) are a kind of novel porous crystal polymers, with highly flexible channel structure and molecular designability. COFs containing nitrogen-rich structures and flexible units can provide effective binding sites for adsorption of iodine, and are potential adsorption materials. In this study, the fully flexible s-triazine-based COFs were prepared by one-pot condensation using fully flexible building blocks of 2,4,6-tris(4-formylphenoxy)- 1,3,5-triazine (TPT–3–CHO) as a knot and ether-based diamines as flexible linkers. The three fully flexible s-triazine-based COFs have large surface areas (1490, 1596, and 1657 m2 g−1), good crystallinity and outstanding adsorption capacitiy of volatile iodine (4.10, 4.13 and 3.40 g g−1) with excellent recyclability. As the linker lengths increase, the specific surface areas increase, but the adsorption amounts of iodine decrease. Moreover, the fully flexible s-triazine-based COFs also have high sensitivities for fluorescence detection against p-nitrophenol and iodine. Their quenching constants (KSV) for p-nitrophenol are 5.59 × 104, 4.05 × 104 and 2.35 × 104 L mol−1, respectively. The fully flexible s-triazine-based COFs have larger specific surface area, high iodine adsorption, and more sensitive fluorescence sensing performance than the COFs formed by the corresponding rigid linkers.

Transmutation of MAs and LLFPs with a lead-cooled fast reactor

The management of nuclear wastes has long been a problem that hinders the sustainable and clean utilization of nuclear energy since the advent of nuclear power. These nuclear wastes include minor actinides (MAs: 237Np, 241Am, 243Am, 244Cm and 245Cm) and long-lived fission products (LLFPs: 79Se, 93Zr, 99Tc, 107Pd, 129I and 135Cs), and yet are hard to be handled. In this work, we propose a scheme that can transmute almost all the MAs and LLFPs with a lead-cooled fast reactor (LFR). In this scheme, the MAs and the LLFPs are loaded to the fuel assembly and the blanket assembly for transmutation, respectively. In order to study the effect of MAs loading on the operation of the core, the neutron flux distribution, spectra, and the keff are further compared with and without MAs loading. Then the LLFPs composition is optimized and the support ratio is obtained to be 1.22 for 237Np, 1.63 for 241Am, 1.27 for 243Am, 1.32 for 79Se, 1.53 for 99Tc, 1.02 for 107Pd, and 1.12 for 129I, respectively, indicating that a self-sustained transmutation can be achieved. Accordingly, the transmutation rate of these nuclides was 13.07%/y for 237Np, 15.18%/y for 241Am, 13.34%/y for 243Am, 0.58%/y for 79Se, 0.92%/y for 99Tc, 1.17%/y for 107Pd, 0.56%/y for 129I. Our results show that a lead-cooled fast reactor can be potentially used to manage nuclear wastes with high levels of long-lived radioactivity.

The Structure, Property, and Ion Irradiation Effects of Pyrochlores: A Comprehensive Review

Since the beginning of the use of nuclear energy, humans have been faced with the problem of radionuclide disposal. At present, a large amount of waste is stored in pools or dry tanks at reactor sites. With the development of the nuclear power generation industry worldwide, the high storage cost (including building, maintaining, and operating storage pools) is overwhelming and serious, and urgent radionuclide disposal problems have become increasingly difficult. Safe and economical strategies are urgently needed for long-term storage and disposal of nuclear waste, which has become among the core issues in the utilization of nuclear energy. Pyrochlore ceramics are able to immobilize a variety of radionuclides and have excellent irradiation stability, so they have received extensive attention as hosts of radionuclides waste. This review summarizes the structure, composition, synthesis process, properties, and irradiation stability of pyrochlore ceramics, focusing on the ion irradiation effect of pyrochlore. In general, the cation radii ratio rA/rB is a key parameter related to various properties of pyrochlores. Zirconate pyrochlore is more easily transformed from pyrochlore to defective fluorite, and leads to better irradiation resistance.

Leaching resistance study on immobilization of MnO2/HMSS with sorbed simulated nuclide strontium by metakaolin-based geopolymers

Radioactive waste generated in nuclear energy utilization poses great environmental risks, and the safe disposal technology has become a hot research topic in the field of nuclear environmental security. Immobilization is a common radioactive waste disposal technique, and the leaching resistance of the solidified body is the key to safe disposal. In the study, metakaolin was used as a raw material to solidify strontium, a common nuclide in radioactive waste streams, and then conducted leaching resistance tests. Using control variables, the experiments were used to investigate the effects of adsorption pretreatment prior to solidifying, solidifying with and without the addition of adsorbent on the effect of immobilization. The leaching resistance of the solidified bodies were investigated in three leaching environments: 25℃ deionized water, pH=1 sulfuric acid solution, and 5%wt magnesium sulfate solution during the 42d test cycle. The results showed that both leaching rate and cumulative leaching fraction of the 42d samples for the leaching resistance of radioactive waste immobilization under the environment of deionized water at 25℃. For the three leaching conditions, the adsorption pretreatment with (4:1)MnO2/HMSS before solidifying or the addition of (4:1)MnO2/HMSS while solidifying could effectively improve the leaching resistance of solidified body, and the former was more effective. The results of this study can provide reference for the disposal of strontium-contanining radioactive waste.

Highly efficient triiodide ion adsorption from water by ionic liquid hybrid metal–organic frameworks

The development and utilization of nuclear energy is one of the effective ways to reduce carbon emissions and achieve the goal of global carbon neutrality. However, it is inevitable to release radioactive pollutants, such as I3−, into the environment during the utilization of nuclear energy, and the efficient adsorption and storage of iodide ion remains a challenge. In this work, a series of ionic liquid (IL) hybrid metal–organic framework (MOF) materials have been developed by simple impregnation of hydrophobic ILs into nanopores of stable MOFs for high-efficient I3− absorption from water for the first time. It is found that the hybrid materal [C2mim][Tf2N]@UiO-67–30 % exhibits a record high I3− absorption capacity at room temperature (4.30 g·g−1), and the I3− absorption capacity of [C2mim][Tf2N] in UiO-67–5 % is 10 times that of the neat [C2mim][Tf2N]. The adsorption process can be well described by Freundlich model and pseudo-second-order model. Such superior I3− absorption capacity is mainly attributed to the multiple sites interaction between anion of the highly dispersed IL and I3−, although cation of the IL and benzene ring of MOF framework also have contribution for the adsorption.

Pengaruh Gradasi Pasir Terhadap Kekuatan Tekan Mortar dalam Perencanaan Sementasi Limbah Radioaktif

Utilization of nuclear energy from various fields of life will produce radioactive waste. Radioactive waste management is carried out according to the type and characteristics of the radioactive waste. Immobilization is an example of a method for managing radioactive waste through compacting or solidifying the waste with a specific matrix to bind and contain the radionuclides. The cementation method is a type of technology for the radioactive waste immobilization method that has been used commercially and proven suitable for use. The main component of cementation is the mortar. This paper aims to determine the effect of fine aggregate (sand) gradation on the compressive strength of the resulting mortar. The research methodology was carried out experimentally. Three types of fine aggregate (sand) are used with IPLN 1, IPLN 2, and IPLN 3 codes. Fine aggregate (sand) has been examined for both silt content (material smaller than 0.075 mm in size), organic content, specific gravity, analysis sand gradation, and fine grain modulus (MHB). From the test results, the fine aggregate (sand) gradations for IPLN 1, IPLN 2, and IPLN 3 are slightly coarse sand, little coarse sand, and fine sand. The fine grain modulus (MHB) of the three types of fine aggregate (sand) are 2.58, 2.46, and 1.8. Only fine aggregate (sand) IPLN 3, whose MHB value is outside the ASTM C33 acceptance criteria, ranges from 2.3 to 3.1. The optimum compressive strength values obtained with three types of fine aggregate (sand) variations, IPLN 1, IPLN 2, and IPLN 3, respectively, were 10.292, 9.411, and 6.026 MPa. Keywords: radioactive waste, cementation, sand, gradation, mortar, compressive strength

Efficient use of solar energy

This paper is mainly about the use of solar energy in life to make a summary, and how to improve the utilization of these aspects to make suggestions. Sunlight transmits electricity to the earth all the time. If the total radiation power from sunlight to the earth is converted into power generation power, it can reach 1.77× kW, which is several hundred million times larger than the current global per capita consumption of electricity. There are not only a lot of sunlight, but also all green energy sources from sunlight, such as wind energy, tidal energy, microbial energy, hydraulic energy, etc., all belong to renewable energy sources. As long as there is sunlight, renewable energy sources are as constant as sunlight. In the process of the efficient development and utilization of solar energy, the photovoltaic utilization of nuclear energy has become the fastest progress around the whole world in recent years, the most vitality of the scientific research field.

Research progress on the hydrogen permeation behavior of the nuclear waste container–A mini review

A large amount of nuclear waste produced in the process of nuclear energy utilization has always been a key problem to be solved urgently for nuclear safety. At present, “deep geological disposal” is a feasible method and is generally accepted by many countries. It is a “multi-barrier system” composed of an artificial barrier, including the solidified waste body, outer packaging material, buffer backfill material, and a natural barrier including the surrounding rock. During deep geological disposal, a near-field environment, where the corrosion of a container could happen, is formed with continuous groundwater infiltration and the release of much heat energy in the process of nuclear waste decay and fission. At the same time, the environment will become a long-term reduction place because of the gradual consumption of the initially retained oxygen. The hydrogen evolution reaction is dominant, so unpredictable hydrogen embrittlement of the container materials could happen due to hydrogen absorption and penetration. This study summarizes the possibility of hydrogen embrittlement of carbon steel, titanium, and their alloys from three aspects, namely, hydrogen solubility, diffusion coefficient, and hydrogen embrittlement, which provides a theoretical basis for predicting the container life in a large time scale.

Thermodynamic analysis and performance evaluation of a novel energy storage-based supercritical CO2 power system with ejector driven by nuclear energy

The application of supercritical CO2 (S-CO2) in power generation systems shows huge advantages of compactness and high efficiency for nuclear energy utilization. However, it is difficult to achieve a quick response for reactor power regulation system in isolated power gird, and amounts of nuclear heat is wasted by bypass regulation to track the power load. In this paper, a novel energy storage-based supercritical CO2 power system with ejector is proposed to realize the rapid energy storage and energy release in system operation to guarantee high conversion efficiency of nuclear energy. Thermodynamic mathematical models are established to examine the performance of the proposed system. The parametric analysis and optimization are performed to acquire the optimum system performance. Furthermore, the performance evaluation in energy storage conditions and energy release conditions are presented to show the power regulation capacity of the proposed system. Results show that the appropriate split ratios of recompression supercritical CO2 power system for different main compressor outlet pressures are both about 0.3. The optimum thermal efficiency of the proposed system is 44.58% and the corresponding exergy efficiency is 66.94% under the given system conditions. In addition, 10% of mass flow rate storage for the S-CO2 results in a decrease in power load of 41.2%, and 10% of mass flow rate release for the S-CO2 can achieve an increase in power load of 45.59%. Furthermore, the maximum regulation capacity for the power load increases with the pressure of the high-pressure energy storage tank. Meanwhile, the energy release conditions with a low pressure of high-pressure energy storage tank and a high entrainment ratio of the ejector result in the decrease in net power output.

Uptake of uranium from wastewater by polyoxometalate modified graphene oxide

Owing to the development and utilization of nuclear energy, an excessive amount of containing uranium wastewater is generated and poses an environmental hazard. In this study, a novel polyoxometalate modified ammoniated graphene oxide (PHGO) was synthesized for the management of radioactive wastewater. The developed adsorbent was investigated by SEM/EDX, AFM, FT-IR, XRD, Raman, TAG and XPS techniques. The effects of pH, reaction time, initial U(VI) concentration, temperature, regeneration time, and co-existing ions on the removal of U(VI) by PHGO were explored. Results show that the maximum adsorption capacity of PHGO for U(VI) was 576 mg/g at pH 5.0, 298 K and 6 h under experimental conditions. In addition, PHGO displayed good stability and adsorption quantity only decreased from 199 mg/g to 150 mg/g after eight cycles. PHGO shows a high efficiency U(VI) removal of 95.4 % (C[U(VI)] = 100 μg /L) for wastewater with variety of metal ions and the residual U(VI) concentration (4.6 μg/L) in wastewater was lower than the most permissible concentration of uranium in drinking water (30 μg/L, World Health Organization). Overall, the PHGO was an excellent adsorbent for extracting uranium.

Significant legal developments concerning “independent” regulatory agencies in the United States and what it could mean for the Nuclear Regulatory Commission

Multiple sources of international nuclear law, including binding instruments such as the Convention on Nuclear Safety (CNS)1 and the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention),2 stress the importance of the independence of the regulator, as well as the effective separation of that regulatory body from others tasked with the promotion or utilisation of nuclear energy. Since its creation in 1974, the United States (US) Nuclear Regulatory Commission (NRC) has been characterised as an “independent agency” within the US government. One of the hallmarks of this independence is that, by law, members of the Commission cannot be removed at will by the President over policy disagreements. However, recent decisions by the US Supreme Court have declared that restrictions on the President’s ability to remove the heads of certain agencies are incompatible with the nation’s constitutional structure and are therefore invalid and unenforceable. As of this writing, these decisions have been limited to independent regulatory agencies headed by a single administrator, not multi-member boards or commissions such as the NRC. However, the Court’s legal reasoning sweeps broadly, and if the holding of these decisions were to be applied to multi-member regulatory bodies (as legal scholars predict), it would shake the organisational bedrock upon which the Commission has rested since its creation. It may also risk transforming the Agency’s public image into that of a political or promotional actor, whose activities are closely overseen by the President who is also responsible for setting energy-related national priorities and goals.

Synthesis of a novel environmental-friendly biocarbon composite and its highly efficient removal of uranium(VI) and thorium(IV) from aqueous solution

The development and utilization of nuclear energy produced a large amount of uranium(VI)/thorium(IV)-containing wastewater, which would be harmful to the environment. The enrichment of the radioactive ions from wastewater using a green and environmentally friendly technology was great important to the protection of water environment and the resource utilization of energy materials. In this work, a novel cow manure-derived biocarbon-based composite was prepared by impregnation-carbonization technology for the separation of thorium(IV) and uranium(VI) from water. The composite could efficiently separate the target ions under acidic condition (pH = 4.5) with high saturated separation capacities (675.1 mg/g for uranium(VI) and 710.4 mg/g for thorium(IV)), high removal percentages (97.5% for uranium(VI) and 99.8% for thorium(IV)), fast separation rates in the initial stage of separation process (10.3 mg/(g·min) for thorium(IV) and 4.6 mg/(g·min) for uranium(VI) and good reusability after five cycles. Even in 1.0 g/L of NaCl solution, the removal efficiencies still exceeded 88.4% for uranium(VI) and 93.1% for thorium(IV). These results exposed the perfect performance of the cow manure-derived biochar-based composite in thorium(IV) and uranium(VI) separation. Moreover, various models were used to fit the experimental data, which revealed that the uranium(VI)/thorium(IV) separation on the biocarbon composite was monolayer chemical adsorption and the complexation was mainly the way for capturing uranium(VI) and thorium(IV). This work might offer a new perspective for the resource management of animal manure and a prospect for the practical application of biochar in thorium(IV) and uranium(VI) recovery.

Electrodeposited iodide ions imprinted polypyrrole@bismuth oxyiodide film for an electrochemically switched renewable extractor towards iodide ions

Effective extraction and regeneration of radioactive iodide is one of urgent concerns for the safe utilization of nuclear energy. As a novel environmentally benign ion separation technique, electrochemically switched ion extraction (ESIE) process can be applied for effective capture and recovery of iodide ions (I − ). Herein, a novel kelp seaweed-like core/shell I − imprinted polypyrrole@bismuth oxyiodide (PPy/I − @BiOI) composite film is successfully prepared for the selective I − capture in the ESIE system. It is found that the I − can be easily trapped in the PPy/I − @BiOI film after I − is in situ desorbed from the film by an electrochemical reduction process since it offers particular electroactive binding sites for I − extraction. The I − imprinted PPy/I − @BiOI film displays an extraction capacity as high as 325.2 mg·g −1 for I − with favorable stability. In particular, the extraction and desorption of I − is achieved by adjusting the redox potential and the pristine PPy/I − @BiOI film can be regenerated and reused for multiple times without decrease in extraction capacity. It is expected that such a PPy/I − @BiOI film would be useful as an electrochemically switched renewable extractor that could capture and regenerate I − from radioactive water.

Evaluasi Indikator Kinerja Keselamatan Reaktor Non Daya

Safety performance indicators (SPI) are observable actions/efforts that provide safety insights directly aimed at measuring how adequately the controls prevent accidents or unwanted incidents. In addition, the SPI is used to identify trends in performance relative to safety objectives, allowing actions to be taken to address unintended changes. Currently, the IAEA has the format for SPI non-power reactors, and BAPETEN has issued Regulation Number 1 of 2017 on Implementation of Inspections in Regulatory of Nuclear Energy Utilization; therefore, it is necessary to evaluate the harmony format of the SPI for non-day reactors. The purpose of this paper is to harmonize the contents of the IAEA version of the SPI with the BAPETEN regulations so that the contents of the IAEA version of the SPI are more detailed. Therefore, all aspects of the IAEA version of the SPI are accommodated in the SPI evaluation result format, and the evaluation version of the SPI format accommodates BAPETEN Regulation Number 1 of 2017. Keywords: safety performance indicator, research reactor.

Suppressed thermal conductivity in hyperstoichiometric uranium dioxide controlled by phonon lifetimes

Thermal transport in nuclear fuels used for nuclear energy applications is directly tied to performance and reliability. Uranium dioxide (UO2), one of the most important nuclear fuels, can accumulate excess oxygen atoms as interstitial defects, which significantly impacts thermal transport properties. In this study, thermal conductivities and inelastic neutron scattering (INS) measurements on UO2+x were performed at low temperatures (2–300 K). The thermal conductivity of UO2+x (x = 0, 0.03, 0.04, and 0.11) is significantly suppressed compared to UO2 except near the Néel temperature TN = 30.8 K, where it is independent of x. INS measurements demonstrate that the heat capacities and phonon group velocities of UO2 and UO2.08 are similar, and the suppressed thermal conductivity results from smaller phonon lifetimes. These perceptions advance our understanding of thermal transport properties in advanced nuclear fuels and guide safe and economic utilization of nuclear energy.

Research on Adhesive Coefficient of Rubber Wheel Crawler on Wet Tilted Photovoltaic Panel

The demand for renewable energy sources is growing fast because of the negative impact of the utilization of fossil energy, nuclear energy, and hydroelectricity. One of the renewable energy sources, known as solar energy, which uses the photovoltaic panel (PV) to generate electricity from the sun, is a promising alternative that has great potential to deal with the power crisis. However, the power productivity and efficiency conversion are affected significantly by dust accumulation on PVs. Many researchers investigated PV panel dust cleaning methods to improve performance, yield, and profitability. Various dust cleaning and mitigation methods such as rainfall, labor-based, and mechanized cleaning are explored, and we demonstrated that dust removal could be automated with cleaning robots effectively. Due to the specified geographical site of PV panel installation, cleaning robots might work on the misalignment and uneven PV arrays, presenting huge challenges for an autonomous cleaning robot. Thus, a rubber wheel crawler robot with semi-autonomous handling provides a flexible motion that is a well-suited solution to clean rooftop PV arrays. Nevertheless, the rubber wheel crawler robot might suffer slippage on the wet glass of tilted PV arrays. This paper studies the anti-slip effect of the rubber wheel crawler equipped with a cleaning robot under the wet surface of tilted PV panels. First, a theoretical model consisting of several parameters is established to validate the slippage of the rubber wheel crawler on the wet tilted PV. Then, some parameters of the theoretical model are approximated through experimental tests. Finally, simulation results of the theoretical model are conducted to evaluate the accuracy of the proposed theoretical model in comparison to the experimental results under the same working conditions. The merits provide the efficient design of rubber wheel crawlers, enabling the anti-slip ability of robots.