Progress in Nuclear Energy最新文献

{"title":"Independent Nuclide Simulation Method (INSM) – A depletion algorithm for simulating the intermediate process of nuclide transmutation","authors":"Dongyuan Li,&nbsp;Qingquan Pan,&nbsp;Xiaojing Liu","doi":"10.1016/j.pnucene.2025.105635","DOIUrl":"10.1016/j.pnucene.2025.105635","url":null,"abstract":"<div><div>Existing depletion algorithms are limited to estimating the final concentrations of nuclides and lack the capability for an in-depth analysis of nuclide transmutation. We propose an Independent Nuclide Simulation Method (INSM), which allows for a detailed nuclide transmutation analysis. In addition to determining the final nuclide concentrations, INSM enables the determination of nuclide transmutation paths, proportions of different reactions, and the conversion rates between nuclides. Implementation involves dividing the whole burnup time into multiple steps, solving nuclide transmutations within each step, and simulating all steps for the entire burnup process. Its simulation process avoids intricate analytical calculations and gives a clear physical image of the real physical process. INSM presents high precision, offering quantitative insights into intermediate information on nuclide transmutation, which is applicable in the field of reactor physics and isotope production.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105635"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140929","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental study on condensation heat transfer of water-ethanol vapour mixtures inside inclined tubes","authors":"Ziqiang Ma ,&nbsp;Yong Li ,&nbsp;Guangyao Liu ,&nbsp;Jun Yang ,&nbsp;Jinshi Wang","doi":"10.1016/j.pnucene.2024.105577","DOIUrl":"10.1016/j.pnucene.2024.105577","url":null,"abstract":"<div><div>Marangoni condensation is a new way to form dropwise condensation mode, which has significant potential applications in the industrial field. However, condensation with binary mixtures inside tubes, which can achieve pseudo-dropwise condensation mode is limited. This study experimentally investigated the heat transfer characteristic of water-ethanol vapour mixtures inside inclined tubes with an inner diameter of 21 mm. Experiments were conducted at inclination angles of 0°, −10°, and −30°, vapour mass fluxes of 10.81, 16.22, 21.62, and 27.03 kg•m⁻²•s⁻¹, coolant flow rates of 1000 and 1800 kg•h⁻¹, and thermal differentials from 15 K to 60 K. The results demonstrated that pseudo-dropwise condensation mode can be formed in the condensation of water-ethanol vapour mixtures inside macro-scale tubes. As vapour mass flux increased, flow regimes transformed from stratified-droplet to wavy-droplet flow. The heat transfer coefficients increased with the increase in coolant flow rates. When the coolant flow rate increased from 1000 to 1800 kg•h⁻¹, condensation heat transfer coefficients in four segments increased by 38.12%, 11.75%, 24.51%, and 9.67%, respectively. The thermal transfer increased with inclination angles in the first condensation segment. Additionally, heat transfer was found to be increased with vapour qualities. These findings provide valuable insights for optimizing heat transfer processes in nuclear systems, where precise control of condensation dynamics is essential for safe and efficient operation.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105577"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141649","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Influence of CHF enhancement by different surfactants in TiO₂ and CNTs hybrid nanofluid on a downward heating plane","authors":"Weiguo Wang,&nbsp;Huai-En Hsieh,&nbsp;Changyue Xu,&nbsp;Hongyi Lv,&nbsp;Zhusheng Guo","doi":"10.1016/j.pnucene.2024.105598","DOIUrl":"10.1016/j.pnucene.2024.105598","url":null,"abstract":"<div><div>Currently, the use of nanofluids to improve Critical Heat Flux (CHF) in pool boiling experiments is a highly important and effective method. This experiment aims to investigate the impact of adding different types of surfactants to nanofluids, as well as the total mass of surfactants and nanoparticles on CHF. The nanofluids used in the experiment are CNT and TiO₂, and the surfactants used include SDBS, SDS, and EG. The experiment was conducted by fixing the mass ratio of the two nanoparticles and dispersants at 1:1:4, while varying the total mass. The experimental results showed that SDBS exhibited the strongest effect on enhancing CHF, achieving a maximum increase of 29.58% at a total mass of 576 mg. To further explore the enhancement mechanism, surface roughness and hydrophilicity were characterized. It was found that there is a significant correlation between the enhancement of CHF and surface roughness and hydrophilicity, leading to the inference of the possible mechanisms by which different surfactants enhance CHF.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105598"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141791","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A novel fully explicit GPU-accelerated discrete element method coupled with moving particle hydrodynamics (DEM-MPH) for simulating the underwater particle sedimentation behavior","authors":"Ryo Yokoyama ,&nbsp;Yihua Xu ,&nbsp;Shuichiro Miwa ,&nbsp;Koji Okamoto","doi":"10.1016/j.pnucene.2025.105615","DOIUrl":"10.1016/j.pnucene.2025.105615","url":null,"abstract":"<div><div>Ensuring the safety integrity of the core catcher system during a hypothetical core disruptive accident (CDA) in a sodium fast reactor (SFR) is crucial, particularly regarding the formation of the debris bed. This study presents a novel, fully explicit Discrete Element Method (DEM) coupled with Moving Particle Hydrodynamics (MPH), accelerated on a graphics processing unit (GPU), to calculate debris bed formation with various particle sizes. The DEM approach is applied to the solid phase, while the liquid phase is calculated using the MPH method. The DEM-MPH method is explicitly updated to avoid significant differences in time steps and to efficiently accelerate calculations on the GPU.</div><div>For validation, a fundamental dam break simulation with tiny particle sizes (0.5 mm) was conducted. The simulation results show good agreement with experimental data in terms of the angle of repose and spread length. Additionally, the GPU-accelerated calculations demonstrated a calculation efficiency of several hundred times improvement compared to a single CPU.</div><div>The DEM-MPH method was also compared to a previous experiment conducted by Sun Yat-Sen University, demonstrating the capability of handling almost 10 million particles. The results indicate that particle size significantly impacts debris bed formation. As particle size decreases, the debris bed shape becomes flatter due to the more significant convection within the liquid pool and the drag force between the solid phase and the liquid. All calculations showed agreement with experimental results regarding debris bed height. Overall, the present DEM-MPH method shows great potential for understanding debris bed formation, which is indispensable for ensuring SFR safety.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105615"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141797","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Feasibility of using thermoelectric generators to power monitoring platforms of SNF canister internal conditions","authors":"Brandon Hager,&nbsp;Mustafa Hadj-Nacer","doi":"10.1016/j.pnucene.2025.105616","DOIUrl":"10.1016/j.pnucene.2025.105616","url":null,"abstract":"<div><div>This paper investigates the feasibility of placing Thermoelectric Generators (TEGs) within spent nuclear fuel dry storage systems to generate electrical power for a wireless monitoring platform of canister internal conditions. This work aims to optimize the placement, dimensions, and thermal properties of the TEGs to maximize the amount of harvested power. Three-dimensional computational fluid dynamics simulations are conducted to optimize TEGs placed within a NUHOMS 61-BT canister stored inside an HSM overpack. Two TEG thicknesses, various locations within the canister, and two different emissivity values are investigated to determine the optimal configuration. The conversion efficiency of the TEGs is assumed to be temperature-dependent, and two TEG figures of merit (1 and 2) are considered. The electric power output of the TEGs and the frequency between measurements are determined for up to 50 years of storage. The results showed that for a canister with an initial total heat generation of 18.3 kW (at 0 years of storage) and a TEG surface area of 0.32 m², the TEGs, with a <span><math><mrow><mi>Z</mi><mi>T</mi></mrow></math></span> value of 1, generate up to 66.10 mW of electric power. At 50 years of storage, they generate 8.85 mW. Assuming an energy consumption of 10.12 J for the wireless monitoring platform, a surface area of 0.1 m² is required to achieve a time between measurements of 8 min at 0 years of storage and 60 min at 50 years of storage.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105616"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141800","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental and numerical study of single bubble migration behavior in stagnant molten LBE","authors":"Songhui Chen ,&nbsp;Qinchuang Cao ,&nbsp;Songbai Cheng ,&nbsp;Hui Cheng","doi":"10.1016/j.pnucene.2025.105609","DOIUrl":"10.1016/j.pnucene.2025.105609","url":null,"abstract":"<div><div>Lead-cooled Fast Reactor (LFR) is generally designed with a pool-typed configuration, where the steam generator heat transfer tube of the secondary loop is in direct contact with high temperature liquid Lead-Bismuth Eutectic (LBE) of the primary loop. Due to the significant temperature and pressure differences between the tube's inner and outer sides, it can lead to a Steam Generator Tube Rupture (SGTR) accident. The migration of steam bubbles in the primary coolant generated by the interaction between LBE and water is a main phenomenon in the fourth stage of SGTR accident. Focusing on this aspect, in current paper experimental and numerical studies are performed on the rising characteristics of bubbles in liquids such as water, ethanol, FC-40, glycerol and molten LBE. In order to qualitatively analyze the bubble motion characteristics during experiments, a high-speed camera is utilized to capture the bubble rising process, and the bubble's position, size, shape and other parameters are obtained. Bubble motion parameters are further extracted from the captured pictures using a self-developed MATLAB image processing code. By investigating the behavior of bubbles as they rise in transparent liquids, the validity of a bubble shape region map and a previous empirical correlation for the estimation of bubble terminal velocity are confirmed. Experimental data for the rising shape and terminal velocity of bubbles in molten LBE are in respectable agreement with the map and empirical correlation. The simulation results of bubble rising behavior in LBE are compared with experiments, which show good consistency in bubble shape and terminal velocity. The experiment and simulation of bubble rising behavior in molten LBE obtained in this study can enhance the understanding of SGTR accident and contribute to future structural design optimization of LFR system.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105609"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140988","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Intelligent control of marine second loop steam discharge system based on variable universe fuzzy control","authors":"Yujin Zhou,&nbsp;Lei Zhang,&nbsp;Wencai Sun,&nbsp;Yuang Shi,&nbsp;Xingru Yang","doi":"10.1016/j.pnucene.2024.105565","DOIUrl":"10.1016/j.pnucene.2024.105565","url":null,"abstract":"<div><div>The steam discharge system plays a crucial role in marine nuclear-powered ships, particularly in ensuring the safety and maneuverability of the nuclear power systems. Traditional marine steam discharge systems typically employ basic open-loop sequential and PID control strategies to manage various discharge conditions. However, as nuclear-powered vessels continue to evolve, the highly nonlinear nature of their power systems has made control increasingly complicated. Issues such as inadequate control precision, significant overshoot, and extended stabilization times have become increasingly problematic for modern integrated electric propulsion vessels, especially those with multiple reactors and turbines. Fuzzy control, emulating human fuzzy reasoning and decision-making, provides exemplary control performance for systems characterized by elusive dynamic characteristics and nonlinearities. In light of this, the paper first establishes a nonlinear model that couples reactors with steam discharge systems and introduces a novel expansion factor to enhance the precision and speed of response of the control system. Building on this foundation, it proposes a new fuzzy controller design. Simulations under typical operational conditions, such as pressure transitions, rapid discharge, maneuvering discharge, safety discharge, and unit startups, are subsequently executed. The results surpass those of the original control logic, offering valuable insights for the development of steam ejection systems in cutting-edge marine vessels.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105565"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141580","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Numerical safety analysis on a conceptual design of fluoride-salt-cooled high-temperature reactors under the influence of ocean conditions","authors":"Limin Liu ,&nbsp;Jiaming Zhang ,&nbsp;Ziyin Liu ,&nbsp;Ziang Guo ,&nbsp;Maolong Liu ,&nbsp;Yao Xiao ,&nbsp;Hanyang Gu","doi":"10.1016/j.pnucene.2024.105579","DOIUrl":"10.1016/j.pnucene.2024.105579","url":null,"abstract":"<div><div>The solid-fuel-type MSR, Fluoride-salt-cooled High-temperature Reactor, presents potential advantages in passive safety, economics and multi-purpose applications. The FHRs applied in ocean conditions face a strong influence on the thermal-hydraulics. Using the modified system analysis code, ASYST, in consideration of the ocean motion effects, the safety evaluation is performed on the FHR concept, MK1 PB-FHR, with the proposed concept designs of the Direct Reactor Auxiliary Cooling System (DRACS). The influence of different heaving and rolling motion conditions is explored on the safety characteristics in the Loss of Forced flow Accident (LOFA). The mass flow rate experiences fluctuation in both of the heaving and rolling conditions. At the same time, the core outlet temperature and fuel maximum temperature do not fluctuate and are close to that in the static conditions. The failure time of the DRACS-2 system will be moved forward in the rolling motion conditions. It is found that MK1 PB-FHR can go through the two types of LOFAs without any safety limits being exceeded in the analyzed ocean motion conditions.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105579"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141585","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor","authors":"Zhitao Tian ,&nbsp;Xinle Wang ,&nbsp;Yuyang Chen ,&nbsp;Hai Zhang ,&nbsp;Huawei Lu","doi":"10.1016/j.pnucene.2024.105595","DOIUrl":"10.1016/j.pnucene.2024.105595","url":null,"abstract":"<div><div>The helium compressor's high-load design approach causes more significant tip-leakage and secondary flow in the passage. Tip injection can effectively restrain the growth of leakage vortex and improve the diffuser capacity of the cascade. In this paper, numerical simulation and wind tunnel experiment are employed to investigate the impact of tip injection on cascade aerodynamic performance in two aspects: axial deflection angles and pitch angles. Under the optimal combination of the injection angle, the effect of tip injection on the cascade performance at different relative positions of guide-rotor blades is investigated. The numerical results demonstrate that an appropriate axial deflection angle enables the leakage vortex with the high-energy fluid to fade on the pressure surface of the adjacent blade, thereby weakening its impact on the downstream flow field. A suitable pitch angle diminishes the strength of the passage vortex formed at the guide vane's trailing edge, which minimizes its mixing with the tip leakage vortex and leakage flow. The injected high-energy flow facilitates the dissipation of the vortex system. The experimental results indicate that tip injection has positive effects on different relative positions of guide-rotor blades, and Case-4 has the most significant improvement effect, with a loss rate of 8.22%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105595"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141594","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and optimization of a 500 kW multi-cylinder double-acting free piston stirling engine for deep-sea nuclear power system","authors":"Siyi Guo,&nbsp;Yongqi Lan,&nbsp;Gen Li","doi":"10.1016/j.pnucene.2024.105588","DOIUrl":"10.1016/j.pnucene.2024.105588","url":null,"abstract":"<div><div>Given the increasing demand for deep-sea exploration, nuclear power system is attracting great interest for electricity supply due to its long-time operation with one refuelling. Double-acting free piston Stirling engine (DAFPSE) is a promising energy conversion system for nuclear power considering its long operation life, low vibration and little maintenance. However, the research on the DAFPSE design and optimization for deep-sea nuclear power system is scarce, which requires high volumetric power density. In this study, a practical isothermal model for designing multi-cylinder DAFPSE was established with the validation against the experiment. Also, the influences of structure parameters, operating parameters and heat exchanger parameters on the DAFPSE performance were investigated. The results indicated that the maximum deviation between the calculation and the experimental result was 8.75%. The compression ratio had significant influence on power density but less influence on efficiency. Specifically, the power density increased by 109.8% and the efficiency decreased by 11.7% respectively when the compression ratio changed from 1.5 to 2. As the engine frequency increased, power density first increased and then decreased, and the maximum power density of 10.71 MW‧m⁻³ was obtained at the frequency of 21 Hz. With the increase of regenerator porosity, the engine efficiency and power density had similar change trends, which showed that the maximum efficiency of 36.6% and the maximum power density of 10.35 MW‧m⁻³ were achieved at the regenerator porosity of 0.8 and 0.9, respectively. The engine efficiency and power density had linear variations with both the hot end temperature and the inlet temperature of cooling water. After the sensitivity investigation of the design parameters, multi-objective optimizations were performed for the structures with different cylinders. The four-cylinder DAFPSE obtained better overall engine performance, in which the optimal scheme was determined from the Pareto optimal frontier with output power of 500.64 kW, power density of 14.00 MW‧m⁻³ and efficiency of 38.02%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105588"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141804","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}