International Journal of Advanced Nuclear Reactor Design and Technology最新文献_第9页

Condensation film flowing dynamics on inclined downward facing plate: Experimental and modeling study 倾斜下平板上凝结膜流动动力学：实验与模型研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-09-01 Epub Date: 2025-02-15 DOI: 10.1016/j.jandt.2025.02.004

Penghui Zhang , Hongbo You

{"title":"Condensation film flowing dynamics on inclined downward facing plate: Experimental and modeling study","authors":"Penghui Zhang , Hongbo You","doi":"10.1016/j.jandt.2025.02.004","DOIUrl":"10.1016/j.jandt.2025.02.004","url":null,"abstract":"<div><div>In-containment refueling water storage tanks have been equipped as an important coolant source for passive cooling systems in the third-generation reactors. Condensate film collection from the containment wall is the key access for its coolant inventory replenishment. On the containment dome, part of the condensate becomes dripping droplets, which cannot be collected and will be a potential loss of the coolant source. Since rare published works are focused on this filed, this work conducts condensation experiments to evaluate the dynamics characteristics of condensate film and droplets with different bulk conditions. A sliced plate of real containment vessel is employed as the condensing plate, with the inclination angle ranging from horizontal to 60°. In the experiments, four condensate flow patterns are recorded and analyzed. It is found Reynolds number of condensates is an important factor that affects condensate flow patterns. Moreover, an empirical model is developed to predict the condensate dripping loss fraction. In addition, global heat transfer coefficients are recorded and compared with the existing semi-empirical model of condensation heat transfer. The findings in this work could be helpful for the evaluation of raining effect and the proposed model could be utilized in the relative reactor analysis codes.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 3","pages":"Pages 222-230"},"PeriodicalIF":0.0,"publicationDate":"2024-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145870987","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Characterization of oxygen transport in a lead-bismuth natural circulation loop 铅铋自然循环回路中氧输运的表征

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-09-01 Epub Date: 2025-02-20 DOI: 10.1016/j.jandt.2025.02.003

Zhenhua Sheng, Tengjun Geng, Shengfei Wang, Fenglei Niu, Fang Liu

{"title":"Characterization of oxygen transport in a lead-bismuth natural circulation loop","authors":"Zhenhua Sheng, Tengjun Geng, Shengfei Wang, Fenglei Niu, Fang Liu","doi":"10.1016/j.jandt.2025.02.003","DOIUrl":"10.1016/j.jandt.2025.02.003","url":null,"abstract":"<div><div>To investigate the oxygen mass transfer characteristics of a lead-bismuth natural circulation loop, numerical simulations of flow, heat transfer, and oxygen mass transfer processes were conducted using COMSOL software. The study found that during the start-up phase of natural circulation, the temperature and flow fields in the expansion tank underwent significant changes. While the oxygen concentration in bismuth could be adjusted dynamically and effectively by setting an appropriate H<sub>2</sub>/H<sub>2</sub>O partial pressure ratio, the mass transfer during this phase accounted for only a small proportion of the overall process. Using a computational model with coupled multiphysics fields, the flow velocity, temperature distribution, and oxygen mass transfer in the liquid bismuth recirculation circuit were calculated. Results indicated that oxygen control, achieved by adjusting the H<sub>2</sub>/H<sub>2</sub>O partial pressure ratio, facilitated both oxygen enrichment and reduction processes. Additionally, the average mass transfer coefficient of interfacial oxygen concentration was positively correlated with heater power and the secondary-side temperature of the heat exchanger. The coefficient changed abruptly when the initial oxygen concentration approached the interfacial oxygen concentration, primarily due to the dominant role of diffusion at that stage. It was further observed that the average mass transfer coefficient remained constant when there were large differences in oxygen concentration, providing valuable insights for predicting the mass transfer efficiency of the entire loop. This study quantitatively analyzed the flow, heat transfer, and oxygen mass transfer characteristics of a lead-bismuth natural circulation loop, offering critical data for experiments and system design.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 3","pages":"Pages 204-211"},"PeriodicalIF":0.0,"publicationDate":"2024-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145870662","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Study on the characteristics of aerosol diffusiophoresis deposition on the outer surface of a vertical circular tube 垂直圆管外表面气溶胶扩散电泳沉积特性研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-09-01 Epub Date: 2025-03-08 DOI: 10.1016/j.jandt.2025.03.002

Junyan Chen , Chao Tian , Shisi Cheng , Haifeng Gu , Dongchuan Ying , Zian Zhai

{"title":"Study on the characteristics of aerosol diffusiophoresis deposition on the outer surface of a vertical circular tube","authors":"Junyan Chen , Chao Tian , Shisi Cheng , Haifeng Gu , Dongchuan Ying , Zian Zhai","doi":"10.1016/j.jandt.2025.03.002","DOIUrl":"10.1016/j.jandt.2025.03.002","url":null,"abstract":"<div><div>The deposition behavior of aerosols due to diffusiophoresis directly influences the migration and deposition of radioactive materials following an accident. This is critical in analyzing source term migration and the precise evaluation of radiological consequences for personnel. Several aerosol deposition experiments were conducted under steam condensation conditions on the external surface of the cooling tube to investigate the diffusiophoresis deposition characteristics of particles in the containment vessel when the PCS system is activated. The experiments demonstrated that the diffusiophoresis deposition rate on the external surface of the cooling tube decreases with increasing steam density but increases with the rise in steam volume fraction. Theoretical analysis combined with data extraction techniques determined the aerosol concentration decay rate on the external surface of the cooling tube under the sole influence of diffusiophoresis. An improved diffusiophoresis deposition model incorporating suction effects was proposed based on relevant heat transfer studies involving non-condensable gases. The comparison of model results showed that the deviation between the improved model and experimental values is within ±10 %, outperforming the predictions of the original model. According to the improved model and experimental results, it was found that a 38 mm tube diameter is more susceptible to the accumulation of incondensable gases, and the suction effect has a more significant promoting influence on diffusiophoresis deposition compared to a 19 mm tube diameter.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 3","pages":"Pages 212-221"},"PeriodicalIF":0.0,"publicationDate":"2024-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145870988","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Thermal analysis of irradiated secondary neutron source assembly with wet transportation 湿输运辐照二次中子源组件的热分析

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-09-01 Epub Date: 2025-03-07 DOI: 10.1016/j.jandt.2025.03.001

Jing-Jing Li , Hai-Jun Liu , Meng-Ying Liu , Bo-Lin Sun

{"title":"Thermal analysis of irradiated secondary neutron source assembly with wet transportation","authors":"Jing-Jing Li , Hai-Jun Liu , Meng-Ying Liu , Bo-Lin Sun","doi":"10.1016/j.jandt.2025.03.001","DOIUrl":"10.1016/j.jandt.2025.03.001","url":null,"abstract":"<div><div>The irradiated secondary neutron source assembly can be used to start-up reactors. After irradiated, secondary neutron source assembly will produce neutron and γ. So, when used to start-up reactors, it is necessary to transport the irradiated secondary neutron source assembly to the target nuclear power unit safely. The irradiated secondary neutron source assembly can be transferred between reactor units by using spent fuel assembly cask. Thermal analysis of wet and dry transportation of irradiated secondary neutron source assembly with a spent fuel transport cask was carried out under normal and accident conditions. The calculation model was validated by the results of safety analysis report of the cask. Under both normal and accident conditions, most of the result errors of this paper are within the range of ±5 %. The calculation result of 4 secondary neutron source assemblies located in the 4 central fuel tube cells of the spent fuel transport cask show that, under normal conditions of wet transportation, the peak temperature of the secondary neutron source assembly rod is about 180 °C, which is about 100 °C lower than that of the dry transportation. Due to the high specific heat of water, temperatures of different parts under wet transport conditions fluctuate at more narrow range than those under dry transport conditions. The peak temperature of the rods is 314.4 °C reached at about 12.7 h after accident under dry transport conditions, while the peak temperature of the rods is 210.7 °C reached at about 38.6 h after accident under wet transport conditions. Compared with dry transportation, wet transportation can not only simplify the process of draining and drying, but also significantly shorten the operation time. Base on the engineering practice experiences, the wet transportation will save about 24 h and 10 bottles of helium during the draining and drying process.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 3","pages":"Pages 231-238"},"PeriodicalIF":0.0,"publicationDate":"2024-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145870660","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 of Portland cement concrete performance at moderately-elevated temperature 中高温条件下硅酸盐水泥混凝土性能试验研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-09-01 Epub Date: 2025-02-21 DOI: 10.1016/j.jandt.2025.02.005

Min Liu , Song Gao , Kefei Li , Qingxun Kong , Rui Zhang

{"title":"Experimental study of Portland cement concrete performance at moderately-elevated temperature","authors":"Min Liu , Song Gao , Kefei Li , Qingxun Kong , Rui Zhang","doi":"10.1016/j.jandt.2025.02.005","DOIUrl":"10.1016/j.jandt.2025.02.005","url":null,"abstract":"<div><div>Concrete, as the most commonly-used construction materials, is used for thousands of structures, including buildings in nuclear power plants. Some concrete structures in nuclear power plants are subjected to moderately elevated temperatures, typically less than 200 °C when operating, but a high-temperature environment can cause degradation of structures. Thus, it is essential to understand the performance of concrete affected by elevated temperature during service life. The concrete high-temperature behavior was explored by conducting mechanical properties tests, permeability test and microstructural test on concrete heated at 65–200 °C for 56 days, and was compared to the identical concrete performance at room temperature. The results show that the moderately-elevated temperature had less impact on concrete compressive and tensile behaviors, but dramatically lowered concrete modulus of elasticity and resistance to chloride penetration. The microstructural change of concrete dominated the performance change of concrete exposed to elevated temperature. Based on experimental results, the long-term performance of concrete in a moderately-elevated temperature environment is predicted.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 3","pages":"Pages 197-203"},"PeriodicalIF":0.0,"publicationDate":"2024-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145870661","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 sodium fire aerosol diffusiophoresis deposition in concrete gaps during the processes within nuclear power plants 核电厂内混凝土间隙中钠火气溶胶扩散电泳沉积的研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-06-01 Epub Date: 2024-12-18 DOI: 10.1016/j.jandt.2024.12.005

Yichen Li, Tiancai Liu, Huanjun Zhu, Xiangyu Yan

{"title":"Investigation of sodium fire aerosol diffusiophoresis deposition in concrete gaps during the processes within nuclear power plants","authors":"Yichen Li, Tiancai Liu, Huanjun Zhu, Xiangyu Yan","doi":"10.1016/j.jandt.2024.12.005","DOIUrl":"10.1016/j.jandt.2024.12.005","url":null,"abstract":"<div><div>Sodium fire accidents are among the high-risk incidents that nuclear power plants with sodium-cooled fast reactors pay close attention to. Sodium fire reactions can generate a considerable amount of heat and aerosols within a short period. To analyze the influence, brought about by the aerosol migration after the sodium fire accident in the process of nuclear power plants, considering the migration process of aerosol particles within the concrete cracks of the walls in it and the concentration changes caused by the steam condensation due to the low-temperature walls. This research establishes a diffusiophoresis model of sub-micron particles under the condition of mixed gas condensation. Simulations were carried out for particles of different sizes under different steam content conditions. The results demonstrate that the diffusiophoresis effect caused by gas condensation within the concrete cracks in the process areas of nuclear power plants has played a positive role in reducing sodium fire aerosol leakage. The penetration coefficient of aerosols within the concrete cracks can be reduced by 6 %. On the one hand, it is discovered that the particle size and steam content have a significant impact on the diffusiophoresis. On average, for every 5 % increase in the steam content in the environment, the penetration coefficient of particles decreases by approximately 2 %. On the other hand, it is found that the aerosol particles generated in the initial stage of the sodium fire reaction and the end of the combustion are more susceptible to the diffusiophoresis effect.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 2","pages":"Pages 171-176"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143100593","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Study on post-accident aerosol retention behavior in microchannels of steel containment in passive nuclear power plants 无源核电站钢壳微通道事故后气溶胶滞留行为研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-06-01 Epub Date: 2024-12-27 DOI: 10.1016/j.jandt.2024.12.006

Yaru Fu, Zeyu Chen, Qiliang Mei, Dawei Sun, Shengqin Gao, Meng Li

{"title":"Study on post-accident aerosol retention behavior in microchannels of steel containment in passive nuclear power plants","authors":"Yaru Fu, Zeyu Chen, Qiliang Mei, Dawei Sun, Shengqin Gao, Meng Li","doi":"10.1016/j.jandt.2024.12.006","DOIUrl":"10.1016/j.jandt.2024.12.006","url":null,"abstract":"<div><div>During an accident at a nuclear power plant, even if the containment is not severely damaged or fails, radioactive aerosols can still leak into the environment through microchannels that potentially exist in the containment. Unlike ordinary gases, radioactive aerosols deposit and get retained in these microchannels through various mechanisms, thereby reducing their leak into the environment. Passive nuclear power plants rely on passive removal mechanisms to eliminate radioactive aerosols, which are highly reliable and effective. The retention of aerosols in microchannels of the containment is also one of the essential passive removal mechanisms. In this work, an analysis model for aerosol retention behavior in microchannels of passive nuclear power plant containment establishes, an analysis software is independently developed, and computational analysis is conducted. The analysis results indicate that when the flow is laminar, the primary removal mechanism of aerosols is inertial impaction at the entrance. When the fluid is turbulent, the removal effect of aerosols is superior to that in laminar flow. In passive nuclear power plants, due to the external spray, most areas are covered by a water film and therefore constituted as wet regions during post-accident stage. When microchannels are in these wet regions, compared to dry regions, aerosol removal effectiveness is enhanced because of the extra removal mechanisms thermophoresis and coagulation.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 2","pages":"Pages 158-163"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143100591","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Machine learning for forecasting factory concentrations of nitrogen oxides from univariate data exploiting trend attributes 利用趋势属性从单变量数据预测工厂氮氧化物浓度的机器学习

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-06-01 Epub Date: 2024-12-12 DOI: 10.1016/j.jandt.2024.12.002

Jiaxin Liu, Shuo Yang, Qichao Li, Leiming Ji, Xuefeng Hou, Liudong Hou, Jing Ma

{"title":"Machine learning for forecasting factory concentrations of nitrogen oxides from univariate data exploiting trend attributes","authors":"Jiaxin Liu, Shuo Yang, Qichao Li, Leiming Ji, Xuefeng Hou, Liudong Hou, Jing Ma","doi":"10.1016/j.jandt.2024.12.002","DOIUrl":"10.1016/j.jandt.2024.12.002","url":null,"abstract":"<div><div>The development of post-processing technology for spent nuclear fuel is essential to ensuring the sustainable growth of nuclear energy. However, post-processing facilities release copious amounts of emissions with high concentrations of nitrogen oxides (NO<sub>x</sub>), making the accurate measurement of their concentrations in radioactive settings greatly challenging. The application of machine learning strategies to predict NO<sub>x</sub> emissions offers a promising approach for improving the measurement and management of NO<sub>x</sub> in post-processing facilities, owing to their potential for cost reduction and operational expediency compared to conventional methods. Therefore, this study presents the outcomes of predictive activities for NO<sub>x</sub> emissions using machine learning. We employed a vector autoregression (VAR) model that considers the influence of other pollutants on NO<sub>x</sub> emissions. The results confirm that the VAR model sufficiently predicts NOx emissions. Furthermore, this study reveals the intricate interplay and feedback loops among various pollutants, thereby providing guidance for formulating comprehensive pollution control strategies. Finally, a lightweight and precise NO<sub>x</sub> forecasting model was developed by extracting the primary features affecting NO<sub>x</sub> predictions. This model has substantial significance for elevating the precision of pollutant emission forecasts and offers substantive support for the development and sustainable growth of the nuclear chemical industry.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 2","pages":"Pages 117-122"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143100892","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Investigate of electrochemical properties of Nd(II) and Nd(III) in eutectic LiCl–KCl molten salt 共晶锂-氯化钾熔盐中钕(II)和钕(III)的电化学特性研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-06-01 Epub Date: 2024-11-07 DOI: 10.1016/j.jandt.2024.10.002

Xinyu Zhang, Wentao Zhou, Dezhong Wang

{"title":"Investigate of electrochemical properties of Nd(II) and Nd(III) in eutectic LiCl–KCl molten salt","authors":"Xinyu Zhang, Wentao Zhou, Dezhong Wang","doi":"10.1016/j.jandt.2024.10.002","DOIUrl":"10.1016/j.jandt.2024.10.002","url":null,"abstract":"<div><div>Pyroprocessing is one of the promising methods to reprocess the spent nuclear fuel. Neodymium (Nd) constitutes about one third of rare earth in fission products, however, the electrochemical properties of Nd have not been thoroughly understood, especially the exchange current. In the present study, the transit electrochemical methods of cyclic voltammetry and square wave voltammetry were applied to study the properties of Nd in LiCl–KCl system. The reduction of Nd<sup>3+</sup> was determined as a two-step reaction with Nd<sup>3+</sup>/Nd<sup>2+</sup> to be a reversible but Nd<sup>2+</sup>/Nd to be a quasi or irreversible reactions. Additionally, parameters such as the diffusion coefficient, exchange current, and apparent potential were derived from the cyclic voltammetry curves. Their relationship with temperature and concentration was investigated under 723 K, 773 K, 823 K with concentrations of 3 wt%, 6 wt% and 9 wt%. The present study contributes significantly to rich the database of Nd in LiCl–KCl molten salt and to understand the electrochemical behaviors of Nd during electrochemical separation of spent nuclear fuel.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 2","pages":"Pages 90-98"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142661127","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident 在模拟严重核反应堆事故条件下对低熔材料进行堆外高温试验的方法

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2024-06-01 Epub Date: 2024-11-07 DOI: 10.1016/j.jandt.2024.10.003

Kuanyshbek Toleubekov , Mazhyn Skakov , Viktor Baklanov , Maxat Bekmuldin , Assan Akaev

{"title":"Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident","authors":"Kuanyshbek Toleubekov , Mazhyn Skakov , Viktor Baklanov , Maxat Bekmuldin , Assan Akaev","doi":"10.1016/j.jandt.2024.10.003","DOIUrl":"10.1016/j.jandt.2024.10.003","url":null,"abstract":"<div><div>This article is devoted to the technique for conducting experiments to study the nature of the interaction of low-melting metals with corium in the conditions of simulating a severe nuclear reactor accident. A feature of such experiments is the need to ensure thermophysical conditions for the occurrence of a severe accident and the organization of the interaction of the metals under study with liquid corium after its obtaining. In this regard, special device for solid metal fragments discharging into liquid corium were designed and manufactured to provide such conditions. At the same time, modeling of the temperature field of the experimental assembly of the VCG-135 test bench to study the interaction between model corium and candidate metal-coolers in the conditions of a severe accident was conducted. The need for modeling is associated with to the probability of metal melting in the discharge device due to the heat flow from the heating crucible of the experimental assembly. The operability of the developed technique was shown as a result of modeling and subsequent experiments at the VCG-135 test bench. The experiments made it possible to obtain products of the interaction of metals with corium for further study of their structural and phase state.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"6 2","pages":"Pages 99-107"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142661087","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0