Nuclear Engineering and Technology最新文献_第7页

Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system 新型mw级紧凑型核电系统被动余热排出系统的设计与分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-09 DOI: 10.1016/j.net.2025.103746

Leqi Yuan, Junli Gou, Zhenlan Wang, Bo Zhang, Jianqiang Shan

{"title":"Design and analysis of passive residual heat removal system for a new MW-class compact nuclear power system","authors":"Leqi Yuan, Junli Gou, Zhenlan Wang, Bo Zhang, Jianqiang Shan","doi":"10.1016/j.net.2025.103746","DOIUrl":"10.1016/j.net.2025.103746","url":null,"abstract":"<div><div>The heat pipe-cooled reactor is an ideal power source for unmanned underwater vehicles (UUVs) due to its compact design, simple structure, and high safety features. However, a heat sink loss accident may lead to reactor damage, requiring a passive residual heat removal system (PRHRS) for emergency cooling. This study presents a novel compact heat pipe reactor with a PRHRS that uses natural circulation to cool the heat pipes' adiabatic sections. A steady-state CFD simulation optimized the geometry, and a transient analysis code was developed in FORTRAN and validated with CFD results. The findings show a sharp increase in fuel temperature immediately after the accident, followed by a decrease as natural circulation cools the reactor. Throughout the accident, component temperatures stayed within permissible limits, with the maximum fuel and heat pipe temperatures not exceeding 965.13 K and 972.5 K, respectively. No boiling occurred in the PRHRS cooling water. This confirms that the PRHRS effectively removes residual heat, ensuring reactor safety during both steady-state and accident conditions, and lays the groundwork for the design of new MW-class compact heat pipe reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103746"},"PeriodicalIF":2.6,"publicationDate":"2025-06-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144280584","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

Research on intelligent hierarchical control method for U-tube steam generator water level based on TD3-MPC 基于TD3-MPC的u型管蒸汽发生器水位智能分级控制方法研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-06 DOI: 10.1016/j.net.2025.103741

Peiqi Jiang , Hong Xia , Jiyu Zhang , Yihu Zhu , Yingying Jiang , Wenhao Ran , Jinxu Pang

{"title":"Research on intelligent hierarchical control method for U-tube steam generator water level based on TD3-MPC","authors":"Peiqi Jiang , Hong Xia , Jiyu Zhang , Yihu Zhu , Yingying Jiang , Wenhao Ran , Jinxu Pang","doi":"10.1016/j.net.2025.103741","DOIUrl":"10.1016/j.net.2025.103741","url":null,"abstract":"<div><div>Aiming at the issues of poor control performance at low power levels and difficulties in precise modeling for U-tube steam generators (UTSG), this paper proposes an intelligent hierarchical control method optimized based on deep reinforcement learning. The primary controller adopts the model predictive control (MPC) algorithm, which directly regulates the water level through an improved objective function. The advanced controller is an agent-based controller utilizing the model-free twin delayed deep deterministic policy gradient (TD3) algorithm, responsible for real-time optimization of the MPC controller parameters. Additionally, to enhance the learning efficiency and convergence performance of the agent, a reward function design framework based on nonlinear scaling and normalization is proposed. Simulation results demonstrate that, compared to traditional methods, the proposed approach achieves precise control of UTSG water level, significantly improves control performance, and enhances adaptive capability and system robustness.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103741"},"PeriodicalIF":2.6,"publicationDate":"2025-06-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366902","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

Verification of the ability of safe activation of the isolated DHR loop of the ALLEGRO reactor in the event of an accident with complete loss of power 验证在完全失去动力的事故中安全激活ALLEGRO反应堆的隔离DHR回路的能力

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-06 DOI: 10.1016/j.net.2025.103734

Pavel Zácha, Václav Železný

{"title":"Verification of the ability of safe activation of the isolated DHR loop of the ALLEGRO reactor in the event of an accident with complete loss of power","authors":"Pavel Zácha, Václav Železný","doi":"10.1016/j.net.2025.103734","DOIUrl":"10.1016/j.net.2025.103734","url":null,"abstract":"<div><div>The development of the ALLEGRO gas-cooled demonstration reactor dates back to the early days of Generation 4 reactors. A more detailed conceptual design is currently being developed, which includes thermohydraulic studies of the reactor's safety features. One of the key components is the emergency residual heat removal system provided by the Decay Heat Removal loop.</div><div>The proper operation of the DHR loop in a total loss of supply accident is strongly dependent on the initial phase of the accident, when helium stagnating throughout the loop volume creates a barrier to the start of its natural circulation in the loop.</div><div>This paper analyze in detail the 3D behavior of the isolated DHR loop both during the normal reactor operation and the operability of the system during the defined accident conditions. The results of the study confirm that the DHR system is designed to be able to safely start the reactor cooling process using natural circulation upon its activation and subsequently cool the hot helium continuously using the DHR exchanger.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103734"},"PeriodicalIF":2.6,"publicationDate":"2025-06-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144307765","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

Method to estimate communication error probabilities based on speech acts for nuclear power plants 基于语音行为的核电厂通信误差概率估计方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-05 DOI: 10.1016/j.net.2025.103740

Ilgeun Song , Taewon Yang , Jonghyun Kim

{"title":"Method to estimate communication error probabilities based on speech acts for nuclear power plants","authors":"Ilgeun Song , Taewon Yang , Jonghyun Kim","doi":"10.1016/j.net.2025.103740","DOIUrl":"10.1016/j.net.2025.103740","url":null,"abstract":"<div><div>Communication errors contribute to safety in nuclear power plants (NPPs), yet they are not explicitly analyzed in conventional human reliability analysis. This limitation makes it challenging to estimate communication error probabilities (CEPs), which play a significant role in understanding human failure events. Current approaches rely on qualitative assessments or lack statistical foundations, impeding the quantification of CEPs in both intra-organizational and inter-organizational communication. To address this, this study proposes a speech act–based method for estimating CEPs in NPP operations. In this method, communication is categorized into five speech acts—Request, Report, Declaration, Acknowledgement, and Recovery—and a procedural communication sequence diagram is developed to model communication sequences, with a specific equation introduced for CEP calculation. To support this calculation, speech act error probabilities are estimated through statistical analysis of observations on simulator training for intra-organizational communication and expert elicitation for inter-organizational communication. A case study was conducted to demonstrate the applicability of the proposed method, analyzing operator failures in starting the high-pressure safety injection system, representing intra-organizational communication, and in deploying a 1 MW mobile gas turbine generator, representing inter-organizational communication. Additionally, performance shaping factors influencing both intra- and inter-organizational CEPs are discussed, providing a foundation for future research.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103740"},"PeriodicalIF":2.6,"publicationDate":"2025-06-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322681","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

Numerical analysis of residual stress in the bending process using kinematic isotropic hardening models for a helical tube in SMR and a U-bent tube in PWR 采用运动各向同性硬化模型对SMR中螺旋管和压水堆中u形管弯曲过程中的残余应力进行了数值分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-03 DOI: 10.1016/j.net.2025.103737

Kyucheol Jeong , Jae-Yoon Jeong , Hyun-Suk Nam , Hyung-Doh Roh , Kwanghyun Ahn , Jonghun Yoon

引用次数: 0

Fuzzy logic-based filtering for defect detection in automated X-ray inspection during the production of lithium-ion battery pouch cells 基于模糊逻辑滤波的锂离子电池袋芯生产过程中x射线检测缺陷检测

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-03 DOI: 10.1016/j.net.2025.103739

Woosung Kim, Jonghyeok Lee, Jiyong Shim, Sanghyun Cho, Hyosung Cho

{"title":"Fuzzy logic-based filtering for defect detection in automated X-ray inspection during the production of lithium-ion battery pouch cells","authors":"Woosung Kim, Jonghyeok Lee, Jiyong Shim, Sanghyun Cho, Hyosung Cho","doi":"10.1016/j.net.2025.103739","DOIUrl":"10.1016/j.net.2025.103739","url":null,"abstract":"<div><div>This paper presents a fuzzy logic-based filtering method for improving defect detection in two-dimensional (2D) automated X-ray inspection (AXI), a nondestructive imaging technique widely used in the inline quality control of lithium-ion batteries (LIBs) during manufacturing. Enhancing the accuracy of defect detection in 2D AXI is crucial for ensuring battery safety; hence, the proposed method combines the outputs of three conventional detection algorithms with a rule-based fuzzy filtering strategy to generate robust defect maps. Experiments were conducted on various types of defects in LIB pouch cells to demonstrate the feasibility of the algorithm. The proposed method significantly improved the detection accuracy, with processing times meeting the strict requirements for inline inspection, as confirmed by qualitative and quantitative evaluations. Specifically, the method achieved a Dice similarity coefficient of 0.98 and an intersection over union of 0.94 for globular foreign material detection, representing improvements of ∼4.3 and 6.8 %, respectively, over conventional algorithms. Furthermore, it achieved an average inference speed of 0.84 frames per second, which is 5.3 times faster than a recent comparative approach. Thus, the proposed method offers a high detection accuracy and practical efficiency, rendering it suitable for industrial deployment in automated inspection systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103739"},"PeriodicalIF":2.6,"publicationDate":"2025-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271356","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

Degradation of the SiGe MMIC LNAs induced by 30 MeV carbon ion irradiation under different bias conditions 不同偏压条件下30 MeV碳离子辐照诱导SiGe MMIC LNAs的降解

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-02 DOI: 10.1016/j.net.2025.103705

Mathew Adefusika Adekoya , Shuhuan Liu , Tian Xing , Junye Zhou , Xuan Wang , Haowei Li , Yunfeng Sun , Chao Wang , Ximin Zhang , Huawei Sheng , Xinkun Li , Xiaotang Ren

{"title":"Degradation of the SiGe MMIC LNAs induced by 30 MeV carbon ion irradiation under different bias conditions","authors":"Mathew Adefusika Adekoya , Shuhuan Liu , Tian Xing , Junye Zhou , Xuan Wang , Haowei Li , Yunfeng Sun , Chao Wang , Ximin Zhang , Huawei Sheng , Xinkun Li , Xiaotang Ren","doi":"10.1016/j.net.2025.103705","DOIUrl":"10.1016/j.net.2025.103705","url":null,"abstract":"<div><div>The SiGe MMIC Low Noise Amplifier (LNA) model BGU7005, fabricated using NXP Semiconductors' QUBiC4 process, is a high-performance amplifier designed for Global Navigation Satellite System (GNSS) applications. We investigate the impact of 30 MeV C<sup>5+</sup> ions irradiation at a fluence of 1 × 10<sup>11</sup> ions cm<sup>−2</sup> on SiGe MMIC LNAs under different conditions. The BGU 7005, operating within 1.5 V–3.1 V voltage supply, was subjected to three conditions: floating, 3V voltage supply, and 3V voltage supply coupled with electromagnetic interference (3V + EMI). The results showed significant post-radiation degradation in key Radio Frequency (RF) parameters. The (3V + EMI) bias condition provides moderate signal transmission and greater stability across the frequencies. However, the floating condition significantly suffers more degradation because of the charge trapping and defect formation. The noise figure (NF) achieves its lowest noise value between 1.5 GHz and 1.6 GHz, beyond 1.6 GHz, radiation exposure increases the noise, particularly affecting the floating and 3V biases. These findings underscore the vulnerability of these devices to radiation-induced damage, particularly in harsh environments. The study highlights that optimized biasing strategies, such as the 3V + EMI condition, are key to mitigating radiation degradation and enhancing LNA reliability in space.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103705"},"PeriodicalIF":2.6,"publicationDate":"2025-06-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144195945","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

Analysis and optimizations of macro-pulse performances for a constructed high-power beam injector with a compact layout 结构紧凑的大功率束流注入器大脉冲性能分析与优化

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-02 DOI: 10.1016/j.net.2025.103730

H. Hu , Y. Wang , H.J. Xu , Y.F. Zeng , T.N. Hu , H.M. Wang , G.Y. Feng , Y.J. Pei

{"title":"Analysis and optimizations of macro-pulse performances for a constructed high-power beam injector with a compact layout","authors":"H. Hu , Y. Wang , H.J. Xu , Y.F. Zeng , T.N. Hu , H.M. Wang , G.Y. Feng , Y.J. Pei","doi":"10.1016/j.net.2025.103730","DOIUrl":"10.1016/j.net.2025.103730","url":null,"abstract":"<div><div>The performance of terahertz (THz) radiation from free electron lasers (FEL) depends on the consistency of electron bunches within the macro-pulse, not just the properties of individual bunches. In accelerator-based injectors, bunch-to-bunch deviations often arise due to transient beam loading effects. This study investigates the impact of such transient responses on macro-pulse inconsistencies by combining theoretical analysis and particle simulations, using the FEL injector at Huazhong University of Science and Technology (HUST) as a case study. The goal is to optimize macro-pulse performance without requiring additional equipment or facility upgrades. To achieve this, an improved multi-objective optimization algorithm, NSGA-III, is introduced to optimize RF injection timing and phase settings, targeting energy and phase consistency within the macro-pulse and stable energy output. The approach is validated through extensive virtual simulations, which demonstrate its effectiveness in providing optimal initial settings for the HUST-FEL injector's macro-pulse. Subsequent online experiments conducted on this injector have preliminarily validated the reliability of the proposed method as well. The results are applicable to other multi-bunch/macro-pulse injectors, offering a cost-effective solution for efficient beam commissioning and engineering implementation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103730"},"PeriodicalIF":2.6,"publicationDate":"2025-06-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271354","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

Experimental study on the minimum limit anchorage length and mechanical properties of bent anchorage steel bars in reactor building 反应堆建筑弯曲锚固钢筋最小极限锚固长度及力学性能试验研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.net.2025.103733

Dayang Wang , Yu Zhang , Yanhu Ding , Mingxin Bai , Zhulin Nie

{"title":"Experimental study on the minimum limit anchorage length and mechanical properties of bent anchorage steel bars in reactor building","authors":"Dayang Wang , Yu Zhang , Yanhu Ding , Mingxin Bai , Zhulin Nie","doi":"10.1016/j.net.2025.103733","DOIUrl":"10.1016/j.net.2025.103733","url":null,"abstract":"<div><div>This study presents a comprehensive investigation into the anchorage performance of bent steel bars embedded in straight segments of reinforced concrete (RC) specimens with high reinforcement ratios, using a prototype nuclear reactor shear wall as the reference model. A total of 44 pull-out tests, grouped into nine series, were conducted to determine the minimum effective anchorage length. Key failure mechanisms, bond behavior, and strain development were systematically analyzed. The results indicated that with decreasing anchorage length, no pull-out failure occurred; instead, steel bar fracture became the dominant failure mode. The minimum effective anchorage length was identified as 0.25l<sub>a</sub>b<sub>e</sub>, below which anchorage performance was significantly compromised. At this critical length, the incorporation of structural transverse reinforcement increased the average maximum yield load by 4.96 %, whereas variations in bent bar length exhibited minimal influence. Furthermore, high reinforcement ratios enhanced the deformation capacity of the specimens, reducing the likelihood of premature yielding. Specimens without transverse reinforcement exhibited a 32.08 % reduction in average yield displacement (9.95 mm) compared to those with transverse reinforcement. An empirical regression model was developed to modify the bond strength calculation under high reinforcement conditions, exhibiting strong predictive accuracy and aligning closely with experimental observations. The findings offer practical insights for the anchorage design of RC specimens in nuclear facilities, especially under conditions of dense reinforcement where existing code provisions may be inadequate.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103733"},"PeriodicalIF":2.6,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144255099","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

Influence of internal heat generation on heat transfer in an MSR heat exchanger under laminar flow condition 层流条件下MSR换热器内部产热对传热的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.net.2025.103736

Dong-Hyuk Park, Bum-Jin Chung

{"title":"Influence of internal heat generation on heat transfer in an MSR heat exchanger under laminar flow condition","authors":"Dong-Hyuk Park, Bum-Jin Chung","doi":"10.1016/j.net.2025.103736","DOIUrl":"10.1016/j.net.2025.103736","url":null,"abstract":"<div><div>A prominent feature of Molten Salt Reactor (MSR) is that the Internal Heat Generation (IHG) occurs within the fluid, as the nuclear fuel is dissolved in the coolant. This renders the energy equation non-homogeneous, requiring different mathematical approach. However, studies that quantitatively analyze the influence of IHG are limited. Especially, in the heat exchanger the IHG occurs coincide with wall cooling. Therefore, we analyzed the influence of IHG on a laminar pipe under wall cooling condition. Based on the superposition principle, the original problem is decomposed into two simpler boundary-layer sub-problems. The presence of IHG increased heat transfer rate and its influence increased with the magnitude of the IHG. Under uniform wall temperature condition, after sufficient flow development, the fluid temperature becomes constant exhibiting a conduction-like behavior, whereas under uniform heat flux condition, the fluid temperature increased despite heat transfer to the wall, superficially resembling a reverse heat transfer. Using the calculated data, the new heat transfer correlations were developed to incorporates the influence of IHG. The correlations were then applied to performance evaluations of MSR heat exchangers. It concludes that neglecting the IHG could lead to an underestimation of total heat transfer rate by up to 26 %. The findings offer a quantitative basis for considering IHG impact in future MSR heat exchanger design.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103736"},"PeriodicalIF":2.6,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271281","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