International Journal of Advanced Nuclear Reactor Design and Technology最新文献

{"title":"Research on fluid-structure interaction of spent fuel storage and transportation basket","authors":"Chen Wang,&nbsp;Jiaojiao Dong,&nbsp;Wei Qin","doi":"10.1016/j.jandt.2025.06.008","DOIUrl":"10.1016/j.jandt.2025.06.008","url":null,"abstract":"<div><div>The structural form of the spent fuel storage and transportation basket is different from that of the traditional rack, and the FSI parameters depend on the structural form. It is uncertain whether the FSI parameters of the traditional rack can meet the needs of the basket. There is no experimental validation for the current FSI parameter calculation method. This paper performs related FSI experiments to verify the accuracy of the numerical simulation method. A numerical simulation model is established with the scale model of the spent fuel storage and transportation basket as the prototype. The simulation is set up strictly in accordance with the experimental conditions. The FSI experiment takes the scale model of the spent fuel storage and transportation basket as the experimental subject, and studies the interactions between the basket and the pool wall as well as between the baskets themselves. Given the initial displacement, the basket vibrates freely. Obtain the FSI parameters. The accuracy of the numerical method is verified by comparing the results of experiment and numerical simulation, and verification data can be supplied for the method of calculating the FSI parameters of the spent fuel storage and transportation basket.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 241-249"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523115","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}

{"title":"Study on the direct measurement method for trace plutonium in samples from spent fuel reprocessing","authors":"Li Li ,&nbsp;Han Yang ,&nbsp;Yingtong Fang ,&nbsp;Xianlong Chang ,&nbsp;Yuning Niu ,&nbsp;Guodu Jiang ,&nbsp;Songtao Yang ,&nbsp;Zhiheng Wang ,&nbsp;Zhaoqing Zhang ,&nbsp;Yurong Li ,&nbsp;Quanwei Liu","doi":"10.1016/j.jandt.2025.06.001","DOIUrl":"10.1016/j.jandt.2025.06.001","url":null,"abstract":"<div><div>To directly, rapidly, and accurately measure trace plutonium in reprocessing samples, two α scintillation counters were developed for the direct measurement of liquids and solids after source preparation. An analytical method for directly determining trace plutonium in process samples was established. Both counters used ZnS(Ag) crystals sprayed onto light-guiding plexiglass as detectors for measuring α nuclide activity concentrations in complex samples containing simultaneous α, β, and γ nuclides. Test results indicated a 75.2 % detection efficiency for the first α scintillation counter for ²³⁹Pu surface sources with good linearity over the concentration range 5 × 10⁻⁶ g/L to 1 × 10⁻³ g/L in aqueous plutonium solutions. It could also directly measure the α activity concentration in aqueous Pu solutions without source preparation. The second α scintillation counter, used a baking-dish measurement method. It exhibited excellent linearity for aqueous plutonium concentrations over 1.0 × 10⁻⁵ to 1 × 10⁻³ g/L with ≤1 % precision in the 5 × 10⁻⁵ to 1 × 10⁻² g/L range. Both systems featured rapid and simple operation.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 195-202"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470284","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}

{"title":"Research on skin dose assessment methods after severe accidents in nuclear power plants","authors":"Meng Li,&nbsp;Dawei Sun,&nbsp;Qiliang Mei,&nbsp;Yaru Fu,&nbsp;Shengqin Gao","doi":"10.1016/j.jandt.2025.06.009","DOIUrl":"10.1016/j.jandt.2025.06.009","url":null,"abstract":"<div><div>In the event of a severe accident at the nuclear power plant, the radioactive plume can cause external immersion exposure and deposition exposure to the skin. The predominant code utilized for estimating the emergency planning zone of the plume, namely the MELCOR Accident Consequence Code System (MACCS), employs excessively conservative assumptions regarding skin deposition dose. As a result, skin dose is hard to meet relevant regulatory requirements. This paper introduces a novel set of conversion factors for the calculation of skin deposition dose and also assesses the immersion skin dose. Furthermore, the analysis encompasses the contributions of various nuclide groups and the impact of meteorological conditions on skin dose levels. The findings reveal that the skin deposition dose is markedly greater than the immersion dose. Specifically, at a distance of 10 km downwind, the immersion external exposure dose is calculated to be 0.01 Sv, whereas the deposition doses calculated from the new conversion factors and MACCS are 0.97 Sv and 1.27 Sv, respectively. This also indicates that deposition dose derived from the new conversion factors is lower than that produced by MACCS. Among six representative release categories, the categories of CI, BP, and CFE exert a more substantial impact on skin dose. For immersion external exposure, it is crucial to consider the contributions from inert gases and iodine, while for deposition external exposure, the primary contributors are rare metals, iodine, and cerium isotopes. The study further indicates that under conditions of constant atmospheric stability, the skin dose initially decreases rapidly with increasing wind speed, followed by a gradual decline.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 235-240"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144501532","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}

{"title":"Study on the evolution and collection characteristics of droplet impact on a collector under space conditions","authors":"Chuyunxi Tang ,&nbsp;Yuan Zhao ,&nbsp;Ruixuan Wei ,&nbsp;Fulong Zhao ,&nbsp;Sichao Tan ,&nbsp;Ruifeng Tian","doi":"10.1016/j.jandt.2025.07.005","DOIUrl":"10.1016/j.jandt.2025.07.005","url":null,"abstract":"<div><div>The Liquid Droplet Radiator (LDR) exhibits superior specific thermal radiation capacity, yet its performance is hindered by droplet splashing and subsequent loss during high-speed collisions with the collector. This paper uses a numerical simulation of five consecutive droplet impacts on a wall in a microgravity environment. It analyzes the collection efficiency and evolution of the droplet collector after multiple droplet collisions. The results show that droplet velocity, diameter, and collector inclination angle affect the dimensional thickness of the liquid film formed after droplet spreading. These factors in turn influence the droplet's evolution and collection characteristics, with the collector inclination angle having the most significant impact. Thinner films, generated under higher velocities, larger diameters, and smaller inclination angles, are directly associated with reduced collection performance. When the droplet velocity is in the range of 17 m/s to 30 m/s, the impact angle is 75°, and the diameter is 400 μm, the collector achieves high collection efficiency, which can provide a reference for the optimized design of droplet coolers.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 284-293"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144633055","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}

{"title":"Numerical simulation of humidification process by spray evaporation under different air pressure and temperature","authors":"Wang Lu ,&nbsp;Kong Mingjuan ,&nbsp;Xiao Rong ,&nbsp;Yan Zheng ,&nbsp;Wei Gang ,&nbsp;Wang Zhaohui ,&nbsp;Bai Wei ,&nbsp;Song Jianjun","doi":"10.1016/j.jandt.2025.06.002","DOIUrl":"10.1016/j.jandt.2025.06.002","url":null,"abstract":"<div><div>In special industrial fields, when dry compressed air enters process fluids containing radioactive substances, it often carries radioactive water vapour. To effectively solve this problem, it is necessary to humidify the dry compressed air before feeding the liquid. By utilizing computational fluid dynamics software FLUENT, this study employs the Discrete Phase Model (DPM) to depict the trajectory of spray particles and investigates the effects of structural parameters and operational variables such as inlet air temperature, inlet pressure, and spray volume on the humidification process. The optimal design parameters for the humidifying tank are determined. The simulation results show that the humidification effect is significantly improved with the increase of inlet air temperature when 30 μ m water droplets are sprayed at a flow rate of 3.8 g/s in a humidification tank with a diameter of 850 mm and a height of 1500 mm; When the water spray volume is increased to 20 g/s, the relative humidity of outlet gas can reach about 91 %; When the installation height of nozzle is 1200 mm, the outlet relative humidity is close to saturation; When nozzles are added, 27 % of the spray water is not involved in the heat and mass transfer process due to spraying to the wall.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 319-330"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828124","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}

{"title":"Effects of feedback color and icon shape on touch interaction performance under unstable conditions of floating nuclear power platforms","authors":"Jing Shui ,&nbsp;Chunhui Dong ,&nbsp;Fuqiu Ma ,&nbsp;Minjun Peng ,&nbsp;Wenxiu Yang","doi":"10.1016/j.jandt.2025.08.003","DOIUrl":"10.1016/j.jandt.2025.08.003","url":null,"abstract":"<div><div>In floating nuclear power platforms (FNPPs), the main control interface will gradually transition from traditional physical control panels to highly integrated, intelligent touchscreens. Existing research on touchscreen interaction performance has primarily focused on static environments. However, its applicability and mechanisms under dynamic sea conditions have not yet been fully elucidated. This study utilized a six-degree-of-freedom motion platform to simulate typical six-degree sea conditions. Through a 3 × 4 two-factor experimental design, the study assessed the impact of three icon shapes (rectangular, circular, triangular) and four color feedback options (green, red, blue, yellow) on touchscreen multi-directional click tasks. The results showed that icon shape and feedback color significantly influenced click efficiency (p &lt; 0.05), with triangular icons combined with yellow feedback performing best in terms of click time and accuracy. This study provides experimental evidence and design recommendations for improving the human-machine interface performance of critical maritime systems such as FNPP.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 351-360"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144911910","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}

{"title":"Research for radiological consequence analysis for extended design case of multiple SGTR accidents","authors":"Zhen Xu,&nbsp;Dawei Sun","doi":"10.1016/j.jandt.2025.07.002","DOIUrl":"10.1016/j.jandt.2025.07.002","url":null,"abstract":"<div><div>In order to verify that the multiple heat transfer tubes rupture of steam generator (SGTR) in the third-generation passive nuclear power plants which use light water as coolant and moderator (TPLWNPPs) will not lead to uncontrolled radioactive release. In this study, RELAP5 and HABIT program were used to study the radioactive consequences of multiple SGTR accidents. Single, 2 and 10 steam generator (SG) heat transfer tubes rupture were considered. The analysis results of these three cases were compared, and the most limiting condition of SGTR accident was given. The results show that the radioactive consequences of single SGTR and multiple SGTR can meet the requirements of acceptance criteria. However, the single SGTR accident is the most limiting, and the dose result margin is the smallest compared with the other two conditions. This study can provide a basis for demonstrating that the radioactive consequences of multiple SGTR accidents can meet the requirements of design expansion conditions (DECs).</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 272-278"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144631393","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}

{"title":"Application of isomorphic remote manipulators with haptic feedback in the development of automatic analysis equipment for spent fuel reprocessing samples","authors":"Li Li ,&nbsp;Dingcan Jin ,&nbsp;Han Yang ,&nbsp;Zhiqiang Wang ,&nbsp;Zhiheng Wang ,&nbsp;Yurong Li ,&nbsp;Quanwei Liu ,&nbsp;Yantao Hu ,&nbsp;Liudong Hou ,&nbsp;Jing Ma","doi":"10.1016/j.jandt.2025.08.002","DOIUrl":"10.1016/j.jandt.2025.08.002","url":null,"abstract":"<div><div>Acid concentration and plutonium valence state in samples are crucial analytical parameters for process control during spent fuel reprocessing. Due to the high radioactivity and strong corrosiveness of reprocessing samples, remote operation is mandatory. A master-slave isomorphic teleoperation robot with haptic feedback function has been developed for the transfer of radioactivity sample in automated analysis devices through program control, which additionally provides manual operation capabilities in a master-slave mode. The isomorphic teleoperation robot was made up of a master arm and a slave arm, the master arm was equipped with an established Universal Robots (UR) system to ensure reliable operation.</div><div>This study develops a radiation-hardened teleoperation system with a gear-coupled slave arm that centralizes electronics in a shielded base. We propose position-force coupling algorithms for precise joint control and a sensorless haptic rendering method enabling real-time force feedback. The design ensures operational fidelity while protecting components in high-radiation environments.</div><div>Notably, compared to cable-driven systems, fully gear-driven manipulators provide superior structural stiffness through rigid meshing transmission, effectively minimizing elastic deformation and backlash. This mechanical advantage is complemented by advanced sensorless force feedback algorithms - notably, the system can translate effective payload on the slave arm into precise feedback force without physical force sensors, enabling real-time force display on the master arm.</div><div>Therefore, the operator can perceive the operating conditions of the slave arm. The master-slave isomorphic remote manipulators had brought safety and efficiency for operations, and has been successfully applied in automatic analysis and equipment maintenance in highly radioactive environments.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 331-340"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144864350","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}

{"title":"Research on container for high-level radioactive waste vitrification product","authors":"Zhinan Yan,&nbsp;Wei Li,&nbsp;Kai Cui,&nbsp;Yinan Xie,&nbsp;Xue Zhang","doi":"10.1016/j.jandt.2025.06.005","DOIUrl":"10.1016/j.jandt.2025.06.005","url":null,"abstract":"<div><div>Product containers for high-level radioactive waste liquid vitrified glass are critical components for ensuring continuous and stable operation of vitrification plants. Given the substantial demand for such containers in China, it is imperative to develop product containers with independent intellectual property rights. This article presented the comprehensive structural design, mechanical analysis and test verification of product containers, considering their usage processes and functional requirements within vitrification plants. The resulting containers exhibited excellent high-temperature resistance, remote-operations, stacking functionality and anti-drop performance, fully meeting the usability and safety demands of the product container in the vitrification plants.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 225-234"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144501534","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}

{"title":"Design and research of an online continuous monitoring instrument for Iodine-129 in reprocessing facilities","authors":"Yang Kang,&nbsp;Cao Ya-Bin,&nbsp;Zhang Wei,&nbsp;Wang Xin","doi":"10.1016/j.jandt.2025.07.001","DOIUrl":"10.1016/j.jandt.2025.07.001","url":null,"abstract":"<div><div>This paper presents the design of an I-129 online continuous monitor based on the I-129 measurement scenario in the reprocessing plant, the characteristics of the NaI(Tl) crystal, the results of MCNP simulation calculations, and the saturation sampling time of the iodine cartridge. This design can effectively mitigate the interference from a large number of Kr-85 nuclides during the I-129 measurement process and satisfy engineering measurement requirements. By correcting the detection efficiency of the I-129 online continuous monitor and integrating this with the instrument design, we derive the calculation formula for I-129 activity concentration, providing theoretical support for instrument program development.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 264-271"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144605298","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}