International Journal of Advanced Nuclear Reactor Design and Technology最新文献_第3页

Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT) 基于NUPEC压水堆试验（PSBT）的空隙率模拟子信道代码LINDEN的验证

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-09-26 DOI: 10.1016/j.jandt.2025.09.006

Yuanbing Zhu, Ke Wang, Ting Wang

{"title":"Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT)","authors":"Yuanbing Zhu, Ke Wang, Ting Wang","doi":"10.1016/j.jandt.2025.09.006","DOIUrl":"10.1016/j.jandt.2025.09.006","url":null,"abstract":"<div><div>Subchannel analysis code is one of the most important thermal-hydraulic analysis tools for nuclear reactor cores. A new subchannel analysis code for PWRs named LINDEN code has been developed by China Nuclear Power Technology Research Institute (CNPRI), and it is also as a part of the self-reliant software package of CNPRI for reactor core design and safety analysis.</div><div>The flow model of the LINDEN code has four conservation equations, and the four-equation flow model is actually a non-equilibrium drift flux model, which takes into account thermal disequilibrium of liquid phase and slip velocity between liquid and vapor phases under sub-cooled boiling condition. In addition, other auxiliary correlations are used for closing these four conservation equations, such as the heat transfer model between fuel rod and coolant, the turbulent mixing model between adjacent subchannels, etc.</div><div>In this paper, the typical NUPEC PWR tests (PSBT) are used to evaluate the void fraction predicable ability of LINDEN. The LINDEN code is used to model and calculate three PSBT void fraction tests, including steady single-channel steady tests, steady 5 × 5 rod bundle tests and transient 5 × 5 rod bundle tests. The calculated void fraction results are compared with the measured results to validate that the LINDEN code has the capability to simulate the void fraction distribution under steady and transient test conditions with acceptable accuracy.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 398-404"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145269217","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

Research on leakage characteristics of labyrinth seal of air turbine used for small mobile reactor 小型移动反应器用空气涡轮迷宫密封泄漏特性研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-10-28 DOI: 10.1016/j.jandt.2025.10.007

Jiabao Lai, Zhenzhen Wang, Zideng Wang, Weixiong Chen, Junjie Yan

{"title":"Research on leakage characteristics of labyrinth seal of air turbine used for small mobile reactor","authors":"Jiabao Lai, Zhenzhen Wang, Zideng Wang, Weixiong Chen, Junjie Yan","doi":"10.1016/j.jandt.2025.10.007","DOIUrl":"10.1016/j.jandt.2025.10.007","url":null,"abstract":"<div><div>Brayton cycle has the characteristics of safety, high efficiency and compactness, which is the primary option for the energy conversion system of small mobile reactors. The performance of the turbine and the thermoelectric conversion efficiency of the system are directly affected by the labyrinth seal. In this study, a computational fluid dynamics (CFD) model of a labyrinth seal was established based on the shaft seal geometry of an air turbine. The effects of different structural parameters such as tooth width, seal clearance, cavity depth, and inclination angle on the labyrinth seal leakage were studied by numerical simulation. The results show that the leakage rate of labyrinth seal increases with the increase of seal clearance. The effect of seal clearance on the leakage is the main factor. With the increase of seal cavity depth, the leakage first decreases and then increases. When the cavity depth increases to a certain value, the leakage tends to remain unchanged. The optimal seal cavity depth-to-width ratio is approximately 0.3. The leakage increases with the increase of seal tooth width. The leakage rate decreases first and then increases with the increase of front inclination angle. The optimal front inclination angle is 90°. The results can provide a reference for the design of labyrinth seal in air turbine.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 459-467"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145418216","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

Research on ventilation of nuclear facilities based on Modelica 基于Modelica的核设施通风研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-10-22 DOI: 10.1016/j.jandt.2025.10.006

Shaodong Yang , Ang Li , Wenzhe Shang , Yuanyuan Li , Sumei Liu , Junjie Liu

引用次数: 0

Research and application of plutonium inventory monitoring system for solution systems 溶液系统钚库存监测系统的研究与应用

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-09-05 DOI: 10.1016/j.jandt.2025.09.002

Xiaoli Hu, Haoran Zhang, Haifeng Yang, Zeng Shao, Miao Yu, Yicheng Zhang

{"title":"Research and application of plutonium inventory monitoring system for solution systems","authors":"Xiaoli Hu, Haoran Zhang, Haifeng Yang, Zeng Shao, Miao Yu, Yicheng Zhang","doi":"10.1016/j.jandt.2025.09.002","DOIUrl":"10.1016/j.jandt.2025.09.002","url":null,"abstract":"<div><div>In order to monitor the plutonium inventory of the solution system, the “point model” equations originated from the nuclear safeguard for plutonium monitoring were improved to make it applicable to the solution system. The assumptions of the improved point model are: 1) the neutron capture without fission is non-negligible, so the leakage multiplication was substituted by the combination of the net multiplication and the leakage multiplication, 2) the difference in energy spectra between (α, n) neutrons and spontaneous fission neutrons was taken into account, 3) the difference in the detection efficiency between spontaneous fission neutrons, (α, n) neutrons and induced fission neutrons was taken into account. According to the improved “point model” equations, the algorithm for the plutonium inventory of the solution system was proposed, which based on the neutron count rate outside the equipment, combined with the composition ratio of the Pu isotopes. And the plutonium inventory estimation program was developed. For a comprehensive test and validation of the algorithm and the program, a series of experiments were designed and carried out, including the neutron detector performance validation experiments carried out in the laboratory, the plutonium solution sample experiments, and the operational data. The validation results demonstrated a good accuracy of the plutonium inventory estimation algorithm for the solution system. The algorithm has been applied to the reprocessing plants for the real-time online NDA monitoring of plutonium.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 361-366"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145121094","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 investigation on the operational characteristics of a steam separator under marine conditions 船用蒸汽分离器运行特性的实验研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-10-29 DOI: 10.1016/j.jandt.2025.09.005

Song Tao , Yang Rui , Tang Shujian , Wu Yu , Li Qipeng , Quan Ziqi

{"title":"Experimental investigation on the operational characteristics of a steam separator under marine conditions","authors":"Song Tao , Yang Rui , Tang Shujian , Wu Yu , Li Qipeng , Quan Ziqi","doi":"10.1016/j.jandt.2025.09.005","DOIUrl":"10.1016/j.jandt.2025.09.005","url":null,"abstract":"<div><div>In this study, a novel steam separator featuring a two-stage separation structure was evaluated for its performance in marine scenes. The operational characteristics of the separator were assessed under various marine conditions. A test rig was designed and constructed to evaluate the vapor-liquid separation performance, and a visualization prototype was developed. Subsequently, test conditions simulating diverse marine environments were established. Using water and air as working fluids, the separation efficiency and flow pressure drop of the visualization prototype were examined under different operating conditions. The uncertainty of the measuring instruments was also analyzed. Results indicate that the steam separator consistently exhibited high separation efficiency, reaching up to 99.8 % while maintaining a flow pressure drop of no more than 1800 Pa under varying marine conditions. Moreover, compared to conventional operational tests, the impact of marine conditions on the separator's operational characteristics was negligible.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 452-458"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145418217","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 pressure variation and its impact on the essential service water system of nuclear power plants 核电站基本给水系统压力变化及其影响研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-10-14 DOI: 10.1016/j.jandt.2025.10.003

Lv Li , Yanyu Yang , Sheng Yan , Xiaolong He , Jiayue Chen , Rongyan Huang , Hong Xu

{"title":"Study on pressure variation and its impact on the essential service water system of nuclear power plants","authors":"Lv Li , Yanyu Yang , Sheng Yan , Xiaolong He , Jiayue Chen , Rongyan Huang , Hong Xu","doi":"10.1016/j.jandt.2025.10.003","DOIUrl":"10.1016/j.jandt.2025.10.003","url":null,"abstract":"<div><div>The Essential Service Water (SEC) system of the CPR1000 unit serves as the ultimate heat sink for the nuclear island system of the power plant. Its distinctive redundant configuration (with standby trains configured) gives rise to specific operational transients, which may induce water hammer phenomena. To investigate this issue, this paper establishes six typical operating conditions of the SEC system using the one-dimensional thermal hydraulic system code RELAP5. It conducts a comparative study on (1) the impact of the operating status of the standby pump on water hammer during startup and shutdown transients, and (2) the impact of gas accumulation in the horizontal pipe after the pump on transient water hammer pressure and the system. The findings demonstrate that pump commissioning triggers nonlinear water hammer effects, and the pressure peaks do not follow a linear superposition principle. Of particular significance, gas accumulation acts as a primary risk amplifier, which notably exacerbates pressure oscillations and elevates pressure peak magnitudes. This research provides critical insights and empirical evidence for optimizing the operational strategy of the SEC system and mitigating water hammer risks, thereby safeguarding the reliability of the ultimate heat sink of CPR1000.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 415-422"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145321871","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 flow and heat transfer characteristics of Li4SiO4 pebble bed based on DEM-CFD coupling 基于DEM-CFD耦合的Li4SiO4球床流动传热特性研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-09-17 DOI: 10.1016/j.jandt.2025.09.003

Fangrui Guo , Qiang Lian , Shanshan Bu , Liangming Pan

{"title":"Study on the flow and heat transfer characteristics of Li4SiO4 pebble bed based on DEM-CFD coupling","authors":"Fangrui Guo , Qiang Lian , Shanshan Bu , Liangming Pan","doi":"10.1016/j.jandt.2025.09.003","DOIUrl":"10.1016/j.jandt.2025.09.003","url":null,"abstract":"<div><div>The blanket is a key component for producing tritium in fusion reactors. To ensure the blanket operates effectively and safely, it is crucial to maintain efficient heat transfer in the pebble bed. Furthermore, the breeder material needs to operate within a specific temperature range to achieve optimal performance. To investigate how temperature influences thermal transport within the pebble bed and enhance the thermal performance of the solid breeder system, this study took the tritium breeder lithium orthosilicate pebble bed as the research object, established a single-size randomly stacked lithium orthosilicate pebble bed model, and studied the temperature-dependent characteristics of internal flow and heat transfer through numerical simulation calculations. The simulation results indicate that gas flow velocity within the pebble bed is affected by the stacking structure of the pebbles. The gas flow velocity increases significantly at locations with larger local pores, and the higher the pebble bed temperature, the greater the increase. Additionally, higher temperatures lead to increased overall bed pressure drop. The effective thermal conductivity of the pebble bed is found to increase as temperature rises, and a correlation formula is fitted to represent its temperature dependence based on the simulation data.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 376-381"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145159693","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

Research on intelligent customization design technology for nuclear power unit systems 核电机组系统智能定制设计技术研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-09-18 DOI: 10.1016/j.jandt.2025.09.004

Yujia Mao , Xinshu Jiang , Meng Zhang , Wei Bai , Rongyong Zhang , Wei Cheng , Kangning Zhou

{"title":"Research on intelligent customization design technology for nuclear power unit systems","authors":"Yujia Mao , Xinshu Jiang , Meng Zhang , Wei Bai , Rongyong Zhang , Wei Cheng , Kangning Zhou","doi":"10.1016/j.jandt.2025.09.004","DOIUrl":"10.1016/j.jandt.2025.09.004","url":null,"abstract":"<div><div>Currently, nuclear power has been accepted by many countries as a safe and clean energy source. According to the nuclear power development policy, China will approve 6–8 units annually. The system of nuclear power plants is complex and highly dense, at present, there are mainly the following characteristics in the design of nuclear power unit systems: there are many design parameters and variables for the nuclear power unit system and its subsystems, which require customized design according to engineering requirements such as plant site and natural environment; The nuclear power unit system and its multiple subsystems require optimization design and multi-attribute decision-making for multiple design schemes from the perspectives of safety and economy. Traditional design is difficult to achieve fast response personalized design in the case of multi unit parallel design. This article elaborates on the exploratory research results of large-scale customization technology for nuclear power unit systems in the “Data Driven Manufacturing Enterprise Intelligent Decision Technology and System” project of the National Key R&D Program of the Ministry of Science and Technology. Based on the design data and experience feedback data of the nuclear power unit system, a demand model and data model were established. A multi-objective optimization algorithm model was developed based on the design hierarchy and optimization calculation characteristics of the nuclear power unit system, and an intelligent optimization design platform for the nuclear power unit system was established. The algorithm model and platform were validated with the design of essential service water systems as the object. The calculation results responded to safety and economic requirements, and compared with traditional design, the design efficiency was improved, and the design parameters could be optimized more quickly.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 388-397"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145222921","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

Maintainable container loader with high repeatability positioning accuracy for use in hot cell 可维护的集装箱装载机，具有高重复性定位精度，适用于热室

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-07-07 DOI: 10.1016/j.jandt.2025.05.006

Si Peng, Xinyi Li, Zelu Yuan, Dehui Wu, Guanchen Zhou, Peng Zhang

{"title":"Maintainable container loader with high repeatability positioning accuracy for use in hot cell","authors":"Si Peng, Xinyi Li, Zelu Yuan, Dehui Wu, Guanchen Zhou, Peng Zhang","doi":"10.1016/j.jandt.2025.05.006","DOIUrl":"10.1016/j.jandt.2025.05.006","url":null,"abstract":"<div><div>In the hot cell, the hermetically sealed transport container must be transferred across multiple workstations prior to placement into the storage well. The minimal clearance between the outer wall of the container and the inner wall of the well necessitates a fully automated transfer process. Accordingly, an automatic container loader with high positioning repeatability and a maintenance-friendly design tailored to the operational conditions of the hot cell is required. Improvements in the positioning repeatability of the gantry and trolley are achieved by implementing a four-wheel drive system, installing horizontal guide wheels, and integrating dual-position feedback mechanisms with calibrated encoders. The accuracy of the hoisting mechanism is further enhanced by combining rigid sleeves with flexible chain lifts. The system is engineered to withstand seismic events. Moreover, considering the unique conditions within the hot cell, redundancy is incorporated into critical components such as drive motors and limit switches to ensure operational safety, and designs that facilitate rapid replacement of vulnerable parts are also included. Comprehensive verification tests of positioning repeatability and maintenance convenience confirm that the container loader meets the expected operational functionalities.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 367-375"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145121095","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

Analysis on the influence law of the rotating reactor supporting roller load affected by manufacturing and installation errors 制造和安装误差对旋转反应器托辊载荷的影响规律分析

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-12-01 Epub Date: 2025-10-22 DOI: 10.1016/j.jandt.2025.10.005

Zhongliang Liu , Xiaodong Gao , Siyao Zhang , Jing Ma , Xiwen Hu , Chen Kan

{"title":"Analysis on the influence law of the rotating reactor supporting roller load affected by manufacturing and installation errors","authors":"Zhongliang Liu , Xiaodong Gao , Siyao Zhang , Jing Ma , Xiwen Hu , Chen Kan","doi":"10.1016/j.jandt.2025.10.005","DOIUrl":"10.1016/j.jandt.2025.10.005","url":null,"abstract":"<div><div>The supporting structure of the rotating wheel is an important component of a certain rotating reactor. In order to improve the safety strength of the rotating reactor, the support system adopts a statically indeterminate structure. Aiming at the influence of the strength of the support rollers and the installation errors on the load, this paper calculates the load on each roller by the force balance equation, adjacent conditions and deformation coordination equation, then the bending stress and contact stress are obtained. A simplified three-dimensional model was established, the stress distribution and variation of each roller were analyzed by finite element software, and the results were verified by experiments. The influence law of manufacturing and installation errors on the total load is analyzed, and the coupling effect of critical errors on the total load is studied. The results show that the maximum bending stress of the roller is 35 MPa, which is far less than the yield strength of the material. The accuracy of the theoretical results is verified by the finite element simulation and the strain test of the roller. The wheel inner radius error Δ<em>R</em><sub>in</sub>, roller outer radius error Δ<em>R</em><sub>g<em>i</em></sub>, roller installation eccentricity Δ<em>a</em><sub><em>i</em></sub> and distribution angle error Δ<em>θ</em><sub><em>i</em></sub> have great influence on the total load, but the other errors have little influence. After considering the coupling effect of critical errors and adjusting the error range according to the results, the total load is generally reduced.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 4","pages":"Pages 476-485"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145520509","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