Progress in Nuclear Energy最新文献_第9页

Dependence in human reliability analysis and in operational events 依赖于人的可靠性分析和操作事件

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-20 DOI: 10.1016/j.pnucene.2025.105991

Luca Podofillini, Vinh N. Dang

{"title":"Dependence in human reliability analysis and in operational events","authors":"Luca Podofillini, Vinh N. Dang","doi":"10.1016/j.pnucene.2025.105991","DOIUrl":"10.1016/j.pnucene.2025.105991","url":null,"abstract":"<div><div>This paper deals with dependencies in accident sequences with multiple Human Failure Events (HFEs). When these are present, the probability of some HFEs may require modification, given knowledge of preceding failures. HFE dependence can have significant impact on Probabilistic Safety Assessment results, because the joint probability of the HFEs may increase by orders of magnitude. State-of-the-art dependence analysis in Human Reliability Analysis (HRA) relies on simplistic approaches with a largely subjective basis. This paper addresses empirical evidence of HRA dependencies from operational events, contributing to ongoing research to strengthen the technical and empirical basis of dependence analysis. This first-of-a-kind analysis of six events identifies three groups of coupling factors: work practice-related, task-related, and knowledge-related. Task-related factors have the strongest influence on dependence because they manifest as specific performance drivers for the multiple tasks. The evaluation of a widely adopted dependence analysis Decision Tree (DT) suggests that the method is practical and adequate for most analysis cases. The analysis identifies some cases for which the DT assessment of independence does not seem appropriate based on the event narrative, e.g. when the DT assessment yields independence (zero dependence) because of an intervening success. As a result, a recommendation is formulated to analysts to question the plausibility of the assessment of independence. The evaluation methodology applied to the DT may also be used to assess more recent modelling developments, also addressing the important need for a larger set of events for broader coverage of situations of interest for HRA.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105991"},"PeriodicalIF":3.2,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144864466","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}

引用次数: 0

Interpretable Bayesian-optimized Autoencoder for fault detection and diagnosis with application in nuclear power plants 可解释贝叶斯优化自编码器在核电厂故障检测与诊断中的应用

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-20 DOI: 10.1016/j.pnucene.2025.105982

Yu Xing , Jiaqiang Wang , Shizhu Cui , Xiaojing Liu , Meiqi Song

{"title":"Interpretable Bayesian-optimized Autoencoder for fault detection and diagnosis with application in nuclear power plants","authors":"Yu Xing , Jiaqiang Wang , Shizhu Cui , Xiaojing Liu , Meiqi Song","doi":"10.1016/j.pnucene.2025.105982","DOIUrl":"10.1016/j.pnucene.2025.105982","url":null,"abstract":"<div><div>Nuclear energy, as an essential clean energy source for combating climate change, is directly tied to sustainable energy development and societal safety through its safe and stable operation. However, fault diagnosis in nuclear power plants faces challenges such as large data volumes, scarcity of fault data, and complex multi-parameter correlations. To address these challenges, this paper proposes an interpretable Bayesian-optimized Autoencoder fault diagnosis model. The model relies solely on normal operating data and accurately diagnoses anomalies through abrupt changes in reconstruction error, overcoming the limitations of traditional methods that depend on fault data. By dynamically adjusting the hyperparameters of the Autoencoder using Bayesian optimization, the model enhances its adaptability to complex time-series data and improves diagnostic precision. Additionally, interpretable machine learning techniques are introduced to quantify the contributions of key parameters to faults, providing clear insights into fault causes and offering scientific support for subsequent engineering interventions. Experimental results demonstrate that the proposed method achieves fault diagnosis F1 scores exceeding 95% on both real-world operational data and simulation datasets from nuclear power plants, significantly outperforming traditional methods. In addition, the model can effectively evaluate the severity of different fault conditions and analyze the cause of the failure, demonstrating strong practical application potential.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105982"},"PeriodicalIF":3.2,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144864467","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}

引用次数: 0

Investigation of the effect of different cations exchanged zeolite for the capture of CH3I for protection of environment 不同阳离子交换沸石对捕获CH3I保护环境的影响研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-20 DOI: 10.1016/j.pnucene.2025.105983

Talhat Yaqoob , Masroor Ahmad , Mohammod Hafizur Rahman , Farman Ali , Amjad Farooq , Mohammad Shahedur Rahman

{"title":"Investigation of the effect of different cations exchanged zeolite for the capture of CH3I for protection of environment","authors":"Talhat Yaqoob , Masroor Ahmad , Mohammod Hafizur Rahman , Farman Ali , Amjad Farooq , Mohammad Shahedur Rahman","doi":"10.1016/j.pnucene.2025.105983","DOIUrl":"10.1016/j.pnucene.2025.105983","url":null,"abstract":"<div><div>The release of radioactive methyl iodide (CH<sub>3</sub>I) during potential accidents at nuclear power plants poses a significant threat to public health and environmental safety. This study recommends a novel material for the capturing of CH<sub>3</sub>I emanating from a NPP using cations (i.e. Ag, Ni, Cu and Zn) exchanged zeolite. The capturing of CH<sub>3</sub>I under conditions relevant to nuclear facilities has been tested with the said material. Raw and modified samples were characterized using several techniques, including SEM-EDX, XRD, AAS, and BET, to reveal their morphology, crystallinity, and chemical composition. Adsorption performance of the modified zeolite materials for non-radioactive methyl iodide (CH<sub>3</sub>I) gas (100 ppm) was evaluated through breakthrough experiments. The UV–visible spectroscopy technique was used for the analysis of the samples. The adsorption performance of gaseous non-radioactive CH<sub>3</sub>I on the surface of zeolite (13X molecular sieve) was evaluated. Breakthrough curves showed that the performance of Ag and Ni-modified zeolite was better than other metal-modified samples. The efficiency of CH<sub>3</sub>I capturing follows this order: Ag > Ni > Cu > Zn. Moreover, the maximum removal efficiency of CH<sub>3</sub>I was obtained up to 627 mg/g under severe conditions. Additionally, adsorption mechanisms of CH<sub>3</sub>I on the surface of modified zeolite were investigated using the Yoon–Nelson and Thomas dynamic adsorption models. Furthermore, the negative Gibbs free energy (ΔG) confirmed that the adsorption processes were spontaneous and exothermic in nature, confirming their thermodynamic favorability under the studied conditions.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105983"},"PeriodicalIF":3.2,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144864468","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}

引用次数: 0

Potential localization strategies and strategic instruments in nuclear power generation 核能发电的潜在国产化策略和战略工具

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-18 DOI: 10.1016/j.pnucene.2025.105993

Ahmet Ege

{"title":"Potential localization strategies and strategic instruments in nuclear power generation","authors":"Ahmet Ege","doi":"10.1016/j.pnucene.2025.105993","DOIUrl":"10.1016/j.pnucene.2025.105993","url":null,"abstract":"<div><div>Deploying the right strategies is of paramount importance and plays a key role in technology transfer to achieve localization. Today, around 30 countries are considering or embarking on nuclear power programs. What are the potential strategies for nuclear power technology localization? This study attempts to identify localization strategies in nuclear technology and also to unfold tested approaches, business models, strategic legal and technical instruments. The methodology of the study treats the nuclear industry in a state as a “unit” in which a variation of PEST analysis is implemented to reveal macro-environmental factors followed by SWOT analysis to identify strengths, weaknesses, opportunities and threats of available approaches, business models, legal and technical instruments. Four principal strategies emerge: (1) learning by doing; (2) transfer, adopt, assimilate, develop and export; (3) own or operate with limited transfer; and (4) wait and see. The first two strategies are proposed for the countries willing to launch an ambitious nuclear power program. Own or operate with limited transfer strategy can be deployed in those countries prioritizing security of supply, source of reliable base load generation, general economic development, technological and qualified human resources development. Wait and see strategy is convenient for those countries awaiting progress of new technologies or phased out nuclear power but planning to reintroduce it in the future. Regardless of the strategy selected, wise guiding policies and coherent set of actions must be deployed for a successful assimilation and acquisition of the design, manufacturing and construction, project engineering and project management in nuclear technology.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105993"},"PeriodicalIF":3.2,"publicationDate":"2025-08-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144860562","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}

引用次数: 0

Chemical states and reactions in multicomponent and multiphase systems containing different nuclide quantities 含有不同核素量的多组分多相体系中的化学状态和反应

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-18 DOI: 10.1016/j.pnucene.2025.105994

Yu Wang , Jingni Guo , Feng Xie , Yuan Liu , Jianzhu Cao , Yujie Dong , Minghua Lyu , Peng Li , Qian Li

{"title":"Chemical states and reactions in multicomponent and multiphase systems containing different nuclide quantities","authors":"Yu Wang , Jingni Guo , Feng Xie , Yuan Liu , Jianzhu Cao , Yujie Dong , Minghua Lyu , Peng Li , Qian Li","doi":"10.1016/j.pnucene.2025.105994","DOIUrl":"10.1016/j.pnucene.2025.105994","url":null,"abstract":"<div><div>Nuclear energy systems are typically multicomponent and multiphase, containing a wide range of nuclides in different quantities, including major, minor and micro elements. In the primary circuit of a nuclear reactor, the fission and activation products generally fall into the micro element category. Investigating the chemical states and reactions of these micro elements presents a significant challenge. In this study, we propose a systematic approach to determining the chemical states and reactions in multicomponent and multiphase systems with varying nuclide quantities, based on fundamental physical principles. To demonstrate the applicability of this method, we utilized the primary circuit of a 10-MW high-temperature gas-cooled experimental reactor (HTR-10). The dominant chemical states of iodine in the primary circuit of HTR-10 were identified as CsI(g), HI(g), and RbI(g). Nine fundamental chemical reactions involving iodine were also identified. Furthermore, the results indicate that the major elements influence both the pressure and chemical potential of minor and micro elements, while minor elements can affect the chemical potential of micro elements. Additionally, the 2-D projected phase diagram developed in this study provides more comprehensive information than traditional 2-D phase diagrams, particularly regarding the relative quantities of components in complex systems.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105994"},"PeriodicalIF":3.2,"publicationDate":"2025-08-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144864500","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}

引用次数: 0

A critical analysis of correlations for saturated nucleate pool-boiling heat transfer over vertical tubes and tube bundles: Development of improved models 垂直管和管束上饱和核池沸腾传热相关性的关键分析：改进模型的发展

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-18 DOI: 10.1016/j.pnucene.2025.105893

Bibhu Bhusan Sha , Rajiva Lochan Mohanty , Mihir Kumar Das

{"title":"A critical analysis of correlations for saturated nucleate pool-boiling heat transfer over vertical tubes and tube bundles: Development of improved models","authors":"Bibhu Bhusan Sha , Rajiva Lochan Mohanty , Mihir Kumar Das","doi":"10.1016/j.pnucene.2025.105893","DOIUrl":"10.1016/j.pnucene.2025.105893","url":null,"abstract":"<div><div>Pool boiling over vertical tubes is vastly experienced in the nuclear industry, where nucleate boiling plays a crucial role in transferring heat. In this context, many experiments have been done in the recent past and developed various correlations for boiling heat transfer. The correlations are influenced by system parameters and the geometrical configuration of the surfaces. Therefore, a wide range of experimental data for saturated pool boiling over vertical tubes and their bundles are taken into consideration to examine the prediction accuracy of various correlations. The prediction errors of various correlations are reported both in tabular and graphical forms. Keeping the most critical parameters in mind, this article proposes two new semi-empirical correlations for predicting the heat transfer coefficient over vertical tubes and their bundles. These developed correlations are able to predict saturated boiling heat transfer coefficients over the tube bundle and single tube data within ±15 % and ±20 %, respectively.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105893"},"PeriodicalIF":3.2,"publicationDate":"2025-08-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144860561","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}

引用次数: 0

Numerical investigation of critical heat flux in single rod channel under extremely low flow conditions 极低流量条件下单杆通道临界热流密度的数值研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-16 DOI: 10.1016/j.pnucene.2025.105980

F.T. Xia , B.Z. Xia , K. Zhang , Zhan Liu , Di Liu , W.X. Tian , S.Z. Qiu

{"title":"Numerical investigation of critical heat flux in single rod channel under extremely low flow conditions","authors":"F.T. Xia , B.Z. Xia , K. Zhang , Zhan Liu , Di Liu , W.X. Tian , S.Z. Qiu","doi":"10.1016/j.pnucene.2025.105980","DOIUrl":"10.1016/j.pnucene.2025.105980","url":null,"abstract":"<div><div>Critical heat flux (CHF) is a crucial thermal parameter influencing reactor safety and efficiency, particularly under extremely low flow conditions. This study analyzes the mechanisms of CHF in a single rod channel under flow conditions ranging from 50 to 300 kg m<sup>−2</sup>·s<sup>−1</sup>,and system pressures of 2–15 MPa, using advanced numerical models, including the Eulerian two-fluid model, interfacial interaction model, and wall boiling model. The simulations show high accuracy, with deviations from experimental data within ±20 %, validating the computational framework. Under these low-flow conditions, CHF is primarily associated with the depletion of the thin liquid film adjacent to the heated surface, where insufficient liquid supply leads to dry-out and severely impairs heat transfer. The parametric analysis reveals that CHF increases with higher inlet subcooling, larger pipe diameters, and higher mass flow rates, while it decreases with longer channel lengths. Pressure has a non-monotonic effect: at lower pressures, CHF increases with pressure, whereas at higher pressures, CHF decreases as pressure increases. These analyses provide deeper insights into the CHF mechanisms under extremely low flow conditions, helping to optimize reactor thermal design and improve safety protocols. This research contributes to the field of thermal-hydraulics in nuclear reactors, offering practical implications for mitigating risks and enhancing energy system performance.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105980"},"PeriodicalIF":3.2,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144852897","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}

引用次数: 0

Uranium removal in aqueous solution by different sizes of commercial Fe3O4 microparticles: key role of oxygen vacancies 不同尺寸的商业Fe3O4微粒对水溶液中铀的去除：氧空位的关键作用

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-16 DOI: 10.1016/j.pnucene.2025.105985

Shizong Wang , Jianlong Wang

{"title":"Uranium removal in aqueous solution by different sizes of commercial Fe3O4 microparticles: key role of oxygen vacancies","authors":"Shizong Wang , Jianlong Wang","doi":"10.1016/j.pnucene.2025.105985","DOIUrl":"10.1016/j.pnucene.2025.105985","url":null,"abstract":"<div><div>Fe<sub>3</sub>O<sub>4</sub> microparticles have been investigated for U(VI) removal. However, the effect of the size of Fe<sub>3</sub>O<sub>4</sub> microparticles on U(VI) removal has not been investigated. Herein, four different sizes (100, 200, 300 mesh, and nano) of commercial Fe<sub>3</sub>O<sub>4</sub> microparticles were used to investigate the size effect on U(VI) removal. The results showed that Fe<sub>3</sub>O<sub>4</sub> microparticles with a size of 200 mesh (Fe<sub>3</sub>O<sub>4</sub>-200) showed the best removal efficiency with a removal capacity of 19.3 mg/g. Characterization analysis showed that Fe<sub>3</sub>O<sub>4</sub> microparticles with 100 and 300 mesh and nano consisted of Fe<sub>3</sub>O<sub>4</sub> phase, whereas Fe<sub>3</sub>O<sub>4</sub>-200 was made up of Fe<sub>2</sub>O<sub>3</sub> and Fe<sub>3</sub>O<sub>4</sub> phase. The combination of Fe<sub>2</sub>O<sub>3</sub> and Fe<sub>3</sub>O<sub>4</sub> phase produced more oxygen vacancies, which endowed Fe<sub>3</sub>O<sub>4</sub>-200 with a superior removal capacity for U(VI). The solution pH affected U(VI) removal by Fe<sub>3</sub>O<sub>4</sub>-200. When the solution pH was 5.0, the U(VI) removal efficiency reached a maximum value. The effect of chloride ions was concentration-dependent, whereas sulfate ions slightly inhibited U(VI) removal. Carbonate ions strongly inhibited U(VI) removal. The U(VI) removal fitted the pseudo-second-order kinetics equation and Langmuir model well. Further thermodynamic analysis proved that Fe<sub>3</sub>O<sub>4</sub>-200 has high reaction ability with U(VI). Fe<sub>3</sub>O<sub>4</sub>-200 can be reused, and the adsorbed U(VI) can be easily recovered using sodium carbonate, sodium acetate, hydrochloric acid and sodium hydroxide. This study provides insight into U(VI) removal by different sizes of Fe<sub>3</sub>O<sub>4</sub> microparticles, and paves a new avenue for designing highly efficient adsorbents for U(VI) removal from water bodies.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105985"},"PeriodicalIF":3.2,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144852896","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}

引用次数: 0

Experimental study on bubble dynamics in narrow rectangular blistering channels – part Ⅱ: Bubble departure 窄矩形起泡通道中气泡动力学的实验研究-部分Ⅱ：气泡偏离

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-16 DOI: 10.1016/j.pnucene.2025.105992

Kexin Liu , Tianzhou Xie , Ming Ding , Xiaxin Cao , Jianjun Xu

{"title":"Experimental study on bubble dynamics in narrow rectangular blistering channels – part Ⅱ: Bubble departure","authors":"Kexin Liu , Tianzhou Xie , Ming Ding , Xiaxin Cao , Jianjun Xu","doi":"10.1016/j.pnucene.2025.105992","DOIUrl":"10.1016/j.pnucene.2025.105992","url":null,"abstract":"<div><div>After the cladding blister of the plate-shaped fuel element occurs, the bubble dynamics in the coolant channel will change, thereby affecting the thermal and hydraulic characteristics of the reactor core. Currently, there is almost no research on bubble dynamics within narrow rectangular blistering channels. As part Ⅱ of the submitted article, this article obtained experimental data on bubble departure diameter and bubble departure frequency based on visualization experiments of narrow rectangular blistering channels. The departure characteristics of rapid condensation bubbles and sliding bubbles were analyzed separately. The geometric structure and thermal parameters were analyzed for their effects on bubble departure diameter and bubble departure frequency. Based on the current experimental data, the existing empirical correlations were evaluated, and it was found that they cannot accurately predict the bubble departure characteristics under blister conditions. The new correlations were proposed for bubble departure diameter and bubble departure frequency applicable to narrow rectangular blistering channels. The predictive ability of new correlations is superior to existing correlations. The accurate modification of the wall boiling model based on the blistering experimental mechanism and new empirical correlations is the direction of future work.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105992"},"PeriodicalIF":3.2,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144852898","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}

引用次数: 0

Numerical study on the effective thermophysical properties of U3Si2/Al dispersion fuel with interaction layer growth 相互作用层生长下U3Si2/Al弥散燃料有效热物理性质的数值研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-16 DOI: 10.1016/j.pnucene.2025.105988

Wenwen Zhang, Wenli Guo, Wentao Hao, Hao Luo, Ding She

{"title":"Numerical study on the effective thermophysical properties of U3Si2/Al dispersion fuel with interaction layer growth","authors":"Wenwen Zhang, Wenli Guo, Wentao Hao, Hao Luo, Ding She","doi":"10.1016/j.pnucene.2025.105988","DOIUrl":"10.1016/j.pnucene.2025.105988","url":null,"abstract":"<div><div>U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel has been widely used in research reactors due to its high uranium density and excellent thermal conductivity. The thermophysical properties of the fuel meat, primarily effective thermal conductivity and specific heat capacity, directly affect the heat dissipation performance and in-core behavior of the fuel. In this study, a refined Representative Volume Element (RVE) model coupled with the Finite Element Method (FEM) is employed to systematically investigate the thermophysical properties of U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel with four different uranium densities. The model incorporates the effects of fuel particle distribution, Interaction Layer (IL) growth, and matrix porosity. The influence of temperature, fuel particle volume fraction, matrix porosity, and IL thickness on the effective thermal conductivity and specific heat capacity is explored. The accuracy of the proposed numerical method is validated by comparison with results from literature-based code and experimentally summarized data. The results indicate that increases in both fuel particle volume fraction and matrix porosity significantly alter the effective thermal conductivity and specific heat. Notably, the growth of the interaction layer reduces the thermal conductivity and modifies the distribution of specific heat capacity. This work provides a theoretical basis for predicting the thermophysical behavior of U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel and offers new insights into fuel design and performance optimization.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105988"},"PeriodicalIF":3.2,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144852899","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}

引用次数: 0