International Journal of Advanced Nuclear Reactor Design and Technology最新文献_第6页

Vibration-absorbing design and comparing research on spent fuel transport cask 乏燃料输送桶吸振设计与比较研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-09-01 Epub Date: 2025-07-10 DOI: 10.1016/j.jandt.2025.07.004

Ziwei Su , Chen Wang , Rui Chen

引用次数: 0

Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise 基于径向平均焓升峰值的反应堆控制棒抛射事故辐射后果分析研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-09-01 Epub Date: 2025-07-04 DOI: 10.1016/j.jandt.2025.07.003

Jie Mao, Qiliang Mei, Shengqin Gao, Dawei Sun, Yaru Fu, Jiaxin Liu

{"title":"Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise","authors":"Jie Mao, Qiliang Mei, Shengqin Gao, Dawei Sun, Yaru Fu, Jiaxin Liu","doi":"10.1016/j.jandt.2025.07.003","DOIUrl":"10.1016/j.jandt.2025.07.003","url":null,"abstract":"<div><div>The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of Reactor Control Rod Ejection Accident (REA). Instead of a set of constant release fractions specified in RG 1.183 (2000), RG 1.183 (2023) has been revised the fuel rod gap release fraction to Steady-State Fission Products Release Fraction (S<sub>FGR</sub>) that are originally residing in the fuel rod gap and Transient Fission Gas Release Fraction (T<sub>FGR</sub>) that are related to burnup and Radial Average Fuel Enthalpy Rise (△H).This paper specifically analyzes the relationship between the fission products release fraction and △H under different burnup, and a set of relatively conservative calculation dose results are obtained based on the empirical data of a specific power plant. In addition, a sensitivity analysis of the effect of △H on the dose consequences is carried out, and the analysis results show that the dose consequences increases linearly with △H when exceeding the critical conditions capable of causing T<sub>FGR</sub>.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 257-263"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144595320","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

Vibration response simulation of centrifuge excited by liquid medium based on SPH-FEM 基于SPH-FEM的液体介质激励下离心机振动响应仿真

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-09-01 Epub Date: 2025-06-18 DOI: 10.1016/j.jandt.2025.06.006

Kan Chen , Lu Chaoran , Guo Mingchao

引用次数: 0

Study on X-ray fluorescence measurement method for Fe content in secondary circuit sampling filter membranes of nuclear power plants 核电厂二次回路取样滤膜铁含量的x射线荧光测量方法研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-09-01 Epub Date: 2025-08-12 DOI: 10.1016/j.jandt.2025.08.001

Yu Zhang, Jin-Zhe Zhang, Hong-Yu Chen

{"title":"Study on X-ray fluorescence measurement method for Fe content in secondary circuit sampling filter membranes of nuclear power plants","authors":"Yu Zhang, Jin-Zhe Zhang, Hong-Yu Chen","doi":"10.1016/j.jandt.2025.08.001","DOIUrl":"10.1016/j.jandt.2025.08.001","url":null,"abstract":"<div><div>The measurement of iron (Fe) content in second-loop sampling filter membranes is critical for evaluating corrosion product deposition in pressurized water reactor (PWR) nuclear power plants. Traditional atomic absorption spectrometry (AAS) methods face challenges such as long prolonged analysis cycles, high operational complexity, and safety risks associated with acid digestion. This study proposes a rapid and non-destructive X-ray fluorescence (XRF) method as an alternative. Standard filter membranes were prepared using Fe<sub>2</sub>O<sub>3</sub> and Fe<sub>3</sub>O<sub>4</sub> oxides via vacuum filtration, and a calibration curve was established for XRF quantification. Results demonstrated a strong linear correlation (R<sup>2</sup> > 0.99) between XRF and AAS measurements, with XRF achieving a lower detection limit (0.51 μg/cm<sup>2</sup> vs. 4.91 μg/cm<sup>2</sup>). Statistical analysis confirmed that XRF meets quantitative accuracy criteria (R<sup>2</sup> = 0.98–0.99) for Fe content analysis in plant filter membranes. The method's feasibility is further validated by addressing matrix effects from oxide morphology and moisture interference. This work provides a reliable approach for real-time monitoring of corrosion products in nuclear systems, reducing reliance on hazardous acid digestion processes.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 341-350"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144888795","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

Dynamic analysis of cold end accident conditions for a space gas-cooled reactor coupled with He–Xe brayton cycle system 空间气冷堆He-Xe布雷顿循环系统冷端事故动态分析

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-09-01 Epub Date: 2025-07-25 DOI: 10.1016/j.jandt.2025.07.007

Tao Liu , Yan Zhang , Chenchen Zhao , Honglei Huo , Quanbin Zhao , Weixiong Chen

{"title":"Dynamic analysis of cold end accident conditions for a space gas-cooled reactor coupled with He–Xe brayton cycle system","authors":"Tao Liu , Yan Zhang , Chenchen Zhao , Honglei Huo , Quanbin Zhao , Weixiong Chen","doi":"10.1016/j.jandt.2025.07.007","DOIUrl":"10.1016/j.jandt.2025.07.007","url":null,"abstract":"<div><div>Space nuclear power systems are promising for deep space missions. As the critical component of the space nuclear power system, radiators' performance significantly impacts both the cycle efficiency and operational safety. However, Radiators occupy a substantial portion of the spacecraft's volume and are highly susceptible to the harsh space environment, which may pose challenges to the system's safety. A dynamic model of the space gas-cooled reactor coupled with He–Xe brayton cycle system was established. Different accident scenarios, such as partial loss of NaK coolant flow and partial heat pipe failure, were simulated. Results indicate that the heat pipe radiator exhibits inherent safety. Under minor accidents, the radiator surface temperature rises to enhance radiative heat dissipation into space, compensating for the accident's impact. Heat accumulation within the radiator caused the operating temperature of heat pipes to rise. Under a NaK coolant flow reduction of 30 %, the maximum heat pipe operating temperature rose by 12.1 % to 473 K. Similarly, a partial failure of 15 % heat pipes led to a 5.4 % increase in maximum operating temperature, reaching 445 K. Notably, both scenarios revealed narrow safety margins for the water heat pipes, as their maximum temperatures only remained 27 K and 55 K below the design limit of 500 K, respectively. Concurrently, these cold-end accident detrimentally affected the system's cycle efficiency. The 30 % NaK flow reduction accident caused a relative decline of 5.79 % in cycle efficiency, while the 15 % heat pipe failure resulted in an efficiency relative drop of 4.66 %. These findings provide reference to the safe operation and control strategies of space nuclear power systems.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 294-307"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144738824","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

Multi-objective optimization of 200 kW air centripetal turbine based on artificial neural networks 基于人工神经网络的200kw空气向心涡轮多目标优化

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 Epub Date: 2025-05-12 DOI: 10.1016/j.jandt.2025.04.013

Zideng Wang, Yan Zhang, Yuyang Leng, Jiabao Lai, Zhenzhen Wang, Weixiong Chen

引用次数: 0

Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage 玻璃固化体暂存自然通风冷却影响因素及结构优化的数值研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 Epub Date: 2025-05-18 DOI: 10.1016/j.jandt.2025.05.005

Yuan Gao , Sihan Liu , Tianci Han , Kai Ma

{"title":"Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage","authors":"Yuan Gao , Sihan Liu , Tianci Han , Kai Ma","doi":"10.1016/j.jandt.2025.05.005","DOIUrl":"10.1016/j.jandt.2025.05.005","url":null,"abstract":"<div><div>Glass curing technology is a mature and effective technical means to deal with high level liquid waste produced by spent fuel reprocessing. The dry storage technology of glass curing body is a developing trend. In the natural ventilation cooling of glass curing body temporary storage, the structural design is crucial, which directly affects the safety and stability of the temporary storage. This paper investigates the effects of various structural parameters and the application of insulating materials on the natural ventilation cooling effectiveness of the temporary storage based on Computational Fluid Dynamics (CFD). The goal is to enhance natural ventilation and reduce the thermal impact of the glass curing body on the concrete structure of the temporary storage. The results show that the height of exhaust shaft, the number of exhaust shaft, the shape of exhaust shaft, annular gap between shaft and glass products, inclination angle of baffle inside intake shaft, the dimensions of intake shaft and ventilation mode are the key factors affecting the ventilation cooling of temporary storage. The cross-sectional area of the air inlet and outlet, and the transverse pitch of glass products have little impact on the ventilation and heat exchange in the temporary storage. The optimal structural arrangement is obtained. The natural ventilation cooling effect is optimal when insulating materials are installed on the top and all four side walls of the temporary storage. The research provides a theoretical basis for the structural design and optimization of glass curing body temporary storage.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 128-138"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189875","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 prediction model of nitrogen oxide concentration in reprocessing plant based on random forest 基于随机森林的后处理厂氮氧化物浓度预测模型研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 Epub Date: 2025-05-09 DOI: 10.1016/j.jandt.2025.04.011

Xuankun Wei, Yan Xu, Xiaomeng Li, Gengxin Fan, Xuening Cheng, Tiantian Yu, Baihua Jiang

引用次数: 0

Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy 轴向燃料混流策略下钠冷却行波堆芯的性能

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 Epub Date: 2025-05-22 DOI: 10.1016/j.jandt.2025.05.007

Meiyin Zheng , Ping Chen , Dalin Zhang , Wenxi Tian , Guanghui Su

{"title":"Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy","authors":"Meiyin Zheng , Ping Chen , Dalin Zhang , Wenxi Tian , Guanghui Su","doi":"10.1016/j.jandt.2025.05.007","DOIUrl":"10.1016/j.jandt.2025.05.007","url":null,"abstract":"<div><div>A prototype sodium cooled traveling wave reactor core with axial fuel shuffling, consist of an ignition and breeding region, was designed in this paper. Neutronic and depletion calculation was performed by MCORE with data library of ENDF/B-VII. A self-developed code SAST was used to perform steady state thermal-hydraulic behavior analysis. The results show that the fluctuation of the reactivity and power peak factor is too big, thus the ignition process should be optimized. The initial nuclide density distribution was adjusted and the axial fuel shuffling option was used to optimize the core ignition process. Results show that the maximum reactivity and radial power peak factor fluctuation are reduced to 1.04 % and 11.76 %; the power density distribution and neutron flux distribution move in the opposite direction of the fuel shuffling; power density, neutron flux and nuclide density are shaped like crescents in the core radial direction during equilibrium cycle; the discharged burn-up of the core is non-uniform, the maximum and minimum discharged burn-up of the outer and inner core are 17.7 % and 70.3 %, respectively. The core flow distribution analysis was based on the end of equilibrium cycle (EOEC) power distribution. Results show that maximum and minimum relative power flow ratio during the whole core life are 1.11 and 0.88; maximum fuel and cladding temperature are 676.9 °Cand 560.0 °C during the whole core life, which have a large safety margin to the design values.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 177-186"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144212543","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 fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network 基于MoCo - Siamese神经网络的核电站旋转机械故障诊断方法研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 Epub Date: 2025-05-07 DOI: 10.1016/j.jandt.2025.04.010

Xia Yubo , Zhao Yanan , Zhao Pengcheng , Zhao Zhengcheng , Yu Tao

{"title":"Research on fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network","authors":"Xia Yubo , Zhao Yanan , Zhao Pengcheng , Zhao Zhengcheng , Yu Tao","doi":"10.1016/j.jandt.2025.04.010","DOIUrl":"10.1016/j.jandt.2025.04.010","url":null,"abstract":"<div><div>Rotating machinery is a kind of significant equipment that widely used in nuclear power plants (NPPs). The harsh operating environment and long-term continuous operation of the rotating machinery can cause various faults due to wear, vibration et al., that threatens the safety of the NPPs. Intelligent fault diagnosis techniques can timely discover the abnormality of the rotating machinery, that received extensively attention in recent years. A fault diagnosis method for NPPs rotating machinery based on MoCo siamese neural network is proposed to address the issues of high noise, small sample, and low accuracy in fault diagnosis under actual operating conditions. The wavelet transform is used to denoise the sensor signals of rotating machinery and extract time-frequency features. The training samples are encoded by the siamese neural network method. The momentum contrast (MoCo) method is used to update the encoder of the siamese neural network. The cosine similarity is used to measure the similarity of sample coding features. The dataset of rotating machinery from Machinery Failure Prevention Technology (MFPT) is adopted to validate the effectiveness and accuracy of the MoCo siamese neural network method. The results shows that the proposed fault diagnosis method has strong noise resistance capability and can accurately diagnose rotating machinery in small sample conditions, demonstrating the potential application value in the fault diagnosis of NPPs rotating machinery.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 187-194"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144253998","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