Annals of Nuclear Energy最新文献_第7页

Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions 流动沸腾中径向空隙率分布的改进CFD建模：一种适用于广泛工况的新方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-08 DOI: 10.1016/j.anucene.2025.111445

Yujiao Peng, Jianqiang Shan, Junliang Guo, Yudong Zha, Miao Gui

{"title":"Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions","authors":"Yujiao Peng, Jianqiang Shan, Junliang Guo, Yudong Zha, Miao Gui","doi":"10.1016/j.anucene.2025.111445","DOIUrl":"10.1016/j.anucene.2025.111445","url":null,"abstract":"<div><div>Accurate prediction of void fraction distribution in flow boiling is of great significance for the thermal–hydraulic analysis and safety of nuclear power plants. Computational Fluid Dynamics (CFD) methods have consistently proven to be effective for boiling simulation. Due to the complexity of boiling phenomena, the prediction of radial void fraction distribution in tubes tends to be challenging, thus hindering a clear understanding of the underlying mechanism. In this work, with the aim of achieving the void fraction prediction over a wide range, the DEBORA experiment operated with R12 was simulated within the pressure range of 1.46–3 MPa and the mass flux range of 1000–5000 kg·m<sup>−2</sup>·s<sup>−1</sup>. The closures of the two-phase equation were compared and the applicability of R12 was discussed. Meanwhile, sensitivity analyses were conducted on the models for bubble departure diameter, lift force, and turbulent dispersion force. The Kocamustafaogullari model was selected for calculating bubble departure diameter. According to the cross-sectional average void fraction, the appropriate selection criteria for the effective turbulent Prandtl number model was recommended. An abnormal upward trend of void fraction near the wall was observed for <em>G</em> ≥ 3000 kg·m<sup>−2</sup>·s<sup>−1</sup> due to the small or even negative relative velocity rather than the lift force coefficient model. A new lift force coefficient model relevant to pressure, mass flux, and void fraction has been proposed. The new CFD model combination demonstrated a good agreement with the experiment, providing an effective tool for analyzing the radial void fraction distribution.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111445"},"PeriodicalIF":1.9,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143792446","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE 流动LBE中多机制耦合腐蚀颗粒沉积模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-07 DOI: 10.1016/j.anucene.2025.111439

Li Liu , Zheng Jia , Ruiqi Bao , Haotian Luo , Junjie Yuan , Hanyang Gu , Pengchen Zhao

{"title":"Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE","authors":"Li Liu , Zheng Jia , Ruiqi Bao , Haotian Luo , Junjie Yuan , Hanyang Gu , Pengchen Zhao","doi":"10.1016/j.anucene.2025.111439","DOIUrl":"10.1016/j.anucene.2025.111439","url":null,"abstract":"<div><div>The accumulation of corrosion products on pipe walls can degrade thermal and flow performance in lead-cooled fast reactor. The objective of this paper is to predict the deposition rates of corrosion products in lead–bismuth eutectic (LBE) using Eulerian deposition model. The model takes into account Brownian diffusion, turbulent diffusion, thermophoresis deposition and convective deposition with acceleration, turbophoresis and steady-state viscous drag. The model also considers the virtual mass force and buoyancy acting on the particles in the high density LBE. Based on the modified model, this paper analyses the mechanism of corrosion particles deposition and investigates the effects of various factors on the deposition rate in detail. Results indicate that diffusion is the primary deposition mechanism of small particles. Both wall roughness and thermophoresis significantly influence particle deposition rate of small particles on the wall. Buoyancy and LBE flow rate also have a significant impact on the particle deposition rate.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111439"},"PeriodicalIF":1.9,"publicationDate":"2025-04-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143785108","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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Novel active disturbance rejection control law design for nuclear reactor power level control in load following operation 核反应堆负荷随运控制的自抗扰控制律设计

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-06 DOI: 10.1016/j.anucene.2025.111410

Boubacar Kirgni Hamza

{"title":"Novel active disturbance rejection control law design for nuclear reactor power level control in load following operation","authors":"Boubacar Kirgni Hamza","doi":"10.1016/j.anucene.2025.111410","DOIUrl":"10.1016/j.anucene.2025.111410","url":null,"abstract":"<div><div>Nuclear reactors are inherently complex systems characterized by significant nonlinearities. Additionally, their operational characteristics evolve over time due to factors such as power levels, aging effects, internal reactivity feedbacks, and fuel burn-up. Given this complexity and variability, nuclear reactors require advanced and highly sophisticated control strategies to ensure both optimal performance and safety throughout their operational lifespan. This paper introduces the design of a novel Active Disturbance Rejection Controller (ADRC) tailored specifically for the load-following process in nuclear reactors. The newly built controller is different from the existing ADRC and not only ensuring closed-loop asymptotic stability but also providing robustness against disturbances. The control performance of the developed ADRC law is assessed through numerical simulation where it has been compared with the traditional Linear ADRC (LADRC) and Model Free Controller (MFC) to show its superiority. It has been demonstrated that the proposed controller can achieve satisfactory tracking performance while rejecting both matched and lumped disturbances.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111410"},"PeriodicalIF":1.9,"publicationDate":"2025-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143783051","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Polyvinyl and bismuth Nitrite based apron (PVABiN-Apron): Fabrication and characterization 聚氯乙烯和亚硝酸盐铋基胶圈（pvabin -胶圈）：制备和表征

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-06 DOI: 10.1016/j.anucene.2025.111446

Fahrul Bakri , Paulus Lobo Gareso , Ali Hamed Alomari , Heryanto Heryanto , Ardiansyah Ardiansyah , Syarifuddin Syarifuddin , Muhammad Khalis Abdul Karim , Ahmad Taufiq , Dahlang Tahir

{"title":"Polyvinyl and bismuth Nitrite based apron (PVABiN-Apron): Fabrication and characterization","authors":"Fahrul Bakri , Paulus Lobo Gareso , Ali Hamed Alomari , Heryanto Heryanto , Ardiansyah Ardiansyah , Syarifuddin Syarifuddin , Muhammad Khalis Abdul Karim , Ahmad Taufiq , Dahlang Tahir","doi":"10.1016/j.anucene.2025.111446","DOIUrl":"10.1016/j.anucene.2025.111446","url":null,"abstract":"<div><div>Developing PVA-based apron samples by incorporating varying concentrations of Bi(NO<sub>3</sub>)<sub>3</sub> (10, 20, 30, and 40 wt%) through a mixing method has been studied. The identified chemical bonds from Fourier transform infrared (FTIR) are O-H, C-H, O=C=O, C=O, NO3<sup>−</sup>, and Bi-O-Bi. The crystallite size from the quantitative analysis of X-ray diffraction (XRD) shows an increase from 8.418 nm to 37.881 nm with increasing Bi(NO<sub>3</sub>)<sub>3</sub> from 10 % to 40 %, respectively. We found that the best concentration is 40 wt% Bi(NO<sub>3</sub>)<sub>3</sub>, indicated by shielding performance’s highest linear attenuation coefficient (LAC) of 17.398 cm<sup>−</sup>1, mass attenuation coefficient (MAC) of 9.719 cm<sup>2</sup>/g, and effective atomic number (Zeff) of 10.943 was evaluated at 80 kVp. Furthermore, this sample exhibited the lowest half-value layer (HVL) of 0.039 cm and the tenth-value layer (TVL) of 0.132 cm, indicating exceptional shielding efficiency. Regarding mechanical properties, the 30 wt% Bi samples achieved the highest tensile strength of 3.888 N/mm<sup>2</sup> and elongation at a break of 18.445 %. These findings suggest that the 40 wt% Bi(NO<sub>3</sub>)<sub>3</sub> apron sample offers a promising lead-free alternative for radiation protection, representing a crucial advancement in sustainable shielding materials. The practical implications of this research are significant, as it could lead to the development of more effective and environmentally friendly radiation protection materials.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111446"},"PeriodicalIF":1.9,"publicationDate":"2025-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143783052","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy 力学参数对Inconel 690合金冲击滑动微动摩擦腐蚀行为的影响

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-06 DOI: 10.1016/j.anucene.2025.111417

Lei Zhang , Guoping Wang , Meigui Yin

引用次数: 0

RSV TAPIRO and TRIGA RC-1 research reactors activities RSV TAPIRO和TRIGA RC-1研究堆活动

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-04 DOI: 10.1016/j.anucene.2025.111409

L. Falconi, V. Fabrizio, A. Santagata

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Transmutation of long-lived fission products (LLFPs) utilizing electron Bremsstrahlung and compact subcritical assembly 利用电子轫致辐射和紧凑型亚临界装配实现长寿命裂变产物（LLFPs）的嬗变

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-03 DOI: 10.1016/j.anucene.2025.111435

Chang M. Kang , Youngin Kim , Jin-Kyu Kim , Won-Gu Kang

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A model predictive control method for sodium-cooled fast reactor 钠冷快堆模型预测控制方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-03 DOI: 10.1016/j.anucene.2025.111416

Shifa Wu , Yunzhi Chai , Jinrong Jin , Areai Nuerlan , Yizhe Liu , Jiashuang Wan

引用次数: 0

Comprehensive validation of fluorine cross-sections 氟横截面的全面验证

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-03 DOI: 10.1016/j.anucene.2025.111426

Tomáš Czakoj , Michal Košťál , Evžen Losa , Vojtěch Rypar , Evžen Novák , Martin Schulc , Bohumil Jánský , Jiří Rejchrt , Tomáš Peltan , Adam Greš , Zdeněk Matěj

{"title":"Comprehensive validation of fluorine cross-sections","authors":"Tomáš Czakoj , Michal Košťál , Evžen Losa , Vojtěch Rypar , Evžen Novák , Martin Schulc , Bohumil Jánský , Jiří Rejchrt , Tomáš Peltan , Adam Greš , Zdeněk Matěj","doi":"10.1016/j.anucene.2025.111426","DOIUrl":"10.1016/j.anucene.2025.111426","url":null,"abstract":"<div><div>The study utilized a PTFE block with a <sup>252</sup>Cf neutron source to measure neutron leakage flux and reaction rate distribution. Hydrogen proportional detectors and stilbene scintillators were employed for spectrum measurement. The experimental setup included various activation foils to measure reaction rates, providing a detailed analysis of neutron interactions with fluorine.</div><div>The results highlighted discrepancies between measured and calculated neutron spectra, emphasizing the need for continuous refinement of nuclear data libraries. The study compared several libraries, including ENDF/B-VIII.0, JEFF-3.3, JENDL-5, and the INDEN fluorine evaluation. It was found that all libraries underpredict measured spectrum in lower energies. Namely below 1.9 MeV in the INDEN fluorine evaluation, below 4.8 MeV in JEFF-3.3 and ENDF/B-VIII.0. JENDL-5 is out of one sigma uncertainty for almost the whole tested energy range.</div><div>Reaction rate measurements further validated the cross-sections, revealing significant discrepancies in the JENDL-5 library in lower energies. The findings underscore the importance of accurate cross-sections for reliable neutron transport simulations. The study advocates for the adoption of updated cross-sections in nuclear data libraries to enhance simulation accuracy.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111426"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759596","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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Best-estimate plus uncertainty analysis of passive air-cooling system for a scale-down integral test facility with GOTHIC 带GOTHIC集成试验装置被动式风冷系统的最佳估计和不确定性分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-03 DOI: 10.1016/j.anucene.2025.111387

Jian Xu , Xu Han , Yunyi Li , Mingrui Yu , Guangliang Chen , Kaiyue Zeng , Yisong Ma , Dongliang Li

{"title":"Best-estimate plus uncertainty analysis of passive air-cooling system for a scale-down integral test facility with GOTHIC","authors":"Jian Xu , Xu Han , Yunyi Li , Mingrui Yu , Guangliang Chen , Kaiyue Zeng , Yisong Ma , Dongliang Li","doi":"10.1016/j.anucene.2025.111387","DOIUrl":"10.1016/j.anucene.2025.111387","url":null,"abstract":"<div><div>Linglong One (ACP100) is a multifunctional modular small pressurized water reactor developed by the China National Nuclear Corporation (CNNC) with independent intellectual property rights. The Passive Containment Air-Cooling System (PAS) is one of the important safety features of ACP100, which can sustainably remove heat from the containment in the event of accidents, ensuring the integrity of the containment. In order to support the engineering application requirements of ACP100 nuclear power plant, the ACP100 containment scaled facility-PAS comprehensive performance test facility (PASE) was built. Its main purpose is to simulate large break loss of coolant accident (LBLOCA) by injecting steam into the containment, in order to verify the cooling capacity of the PAS under LBLOCA conditions. In this paper, for PASE, the best-estimate code GOTHIC was used to investigate LBLOCA, and the natural air-cooling capability of the PAS under severe accident scenarios was evaluated by the associated uncertainty assessment. The validity and usability of the GOTHIC model were verified through comparative analysis of PASE experimental data with GOTHIC calculation results, and the important thermal–hydraulic phenomena of the experimental process were also analysed. Subsequently, uncertainty analysis was conducted based on the Code Scaling, Applicability and Uncertainty (CSAU) methodology, and 12 important input uncertain parameters were selected. The 95th/95% uncertainty bands of the key output parameters were obtained based on the Wilks’ nonparametric statistics, as well as batch running of the code in conjunction with the G-Shell software package. Finally, sensitivity analyses by Spearman rank correlation coefficient were performed to identify important input uncertain contributors to the comprehensive performance of PAS.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111387"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759597","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0