Nuclear Engineering and Technology最新文献_第4页

Analytical derivation of steady-state delayed neutron precursor distribution and effective delayed neutron fraction in a molten salt reactor 熔盐堆中稳态延迟中子前体分布和有效延迟中子分数的解析推导

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-23 DOI: 10.1016/j.net.2026.104160

Jae Jun Jeong , Yun Je Cho

{"title":"Analytical derivation of steady-state delayed neutron precursor distribution and effective delayed neutron fraction in a molten salt reactor","authors":"Jae Jun Jeong , Yun Je Cho","doi":"10.1016/j.net.2026.104160","DOIUrl":"10.1016/j.net.2026.104160","url":null,"abstract":"<div><div>In liquid-fueled molten salt reactors (MSRs), the nuclear fuel is dissolved in a molten salt mixture that circulates through the primary loop. For system-scale simulations of MSRs, a point kinetics model (PKM) is commonly employed to describe the core neutronic behavior. In this model, flow-related terms are added to the delayed neutron precursor (DNP) balance equation by simplifying the reactor system into two lumped regions - a reactor core and an external loop. This simplified approach is, however, inadequate for a realistic MSR system with complex flow paths. To overcome this limitation, a DNP transport equation can be incorporated into the PKM in place of the DNP balance equation, enabling a more accurate representation of the DNP distribution throughout the reactor system.</div><div>In this study, a one-dimensional thermal-hydraulic model is assumed for MSR system simulations, and the axial power distribution in the reactor core is considered to be either uniform or sinusoidal. Analytical solutions to the steady-state DNP transport equation are then derived to obtain one-dimensional DNP profiles in the core and the corresponding effective delayed neutron fraction. These analytical results can serve as reference solutions for verifying thermal-hydraulic system codes developed for MSRs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104160"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146090477","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

Neutron and γ-ray shielding properties of magnetite-serpentine concrete based on Geant4 simulation 基于Geant4模拟的磁铁矿蛇纹混凝土中子和γ射线屏蔽性能

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-12 DOI: 10.1016/j.net.2026.104127

Jun Liu , Hongfei Chen , Weizhuo Zhang , Renjie Niu , Ertao Li , Yuyang Chen

{"title":"Neutron and γ-ray shielding properties of magnetite-serpentine concrete based on Geant4 simulation","authors":"Jun Liu , Hongfei Chen , Weizhuo Zhang , Renjie Niu , Ertao Li , Yuyang Chen","doi":"10.1016/j.net.2026.104127","DOIUrl":"10.1016/j.net.2026.104127","url":null,"abstract":"<div><div>Serpentine concrete is an excellent neutron shielding material, and the addition of magnetite aggregate can enhance the γ-ray shielding performance of concrete. In this study, the Geant4 software was used to simulate and analyze five different concrete mix designs where magnetite aggregate replaced serpentine aggregate at varying concentrations. To ensure the reliability of the simulation results, the study compared them with the calculated data obtained from the Phy-X/PSD program. For both neutrons and γ-rays, several shielding parameters including linear attenuation coefficient (<em>μ</em>), half-value layer (HVL) and effective atomic number (<em>Z</em><sub><em>eff</em></sub>) as well as effective electron density (<em>N</em><sub><em>eff</em></sub>) were systematically calculated. Penetration rate and neutron energy spectrum analyses were also conducted. The results show that with the increase of magnetite doping, the γ-ray shielding performance of concrete is significantly enhanced, but the neutron shielding ability decreases. Based on a comprehensive evaluation of various performance indicators, the optimal proportion of magnetite aggregate was determined to be 25 %. The neutron shielding performance of this admixture is similar to that of pure serpentine concrete, while its γ-ray shielding performance is significantly improved.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104127"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980452","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

Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code 使用STREAM中子码对SPERT III E-core临界实验进行基准分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2025-12-31 DOI: 10.1016/j.net.2025.104112

Anisur Rahman , Saisundar Mohanty , Deokjung Lee

{"title":"Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code","authors":"Anisur Rahman , Saisundar Mohanty , Deokjung Lee","doi":"10.1016/j.net.2025.104112","DOIUrl":"10.1016/j.net.2025.104112","url":null,"abstract":"<div><div>This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs). Using the advanced 3D transport code STREAM, we construct a detailed full-core representation—including fuel assemblies, cruciform transient control rods, control rod followers, and flux suppressors, to simulate both steady-state operation and rapid power excursions. Eigenvalue predictions at cold and hot zero-power conditions agree with measurements within 400 pcm, while simulated RIA responses, including reactivity evolution, peak power, and energy release, remain within 10 % of experimental observations. These results demonstrate that STREAM reliably captures fast transient dynamics in complex reactor configurations. Beyond validating a modern deterministic tool against historically important pulse-reactor experiments, this work establishes a foundation for next-generation transient modeling, supporting enhanced safety assessment, performance optimization, and informed regulatory decision-making in advanced reactor systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104112"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980449","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

Seismic behavior of electrical cabinets with cast-in-place anchors: influence of concrete cracks and multi-bay installation 现浇锚杆电柜抗震性能：混凝土裂缝和多槽安装的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-16 DOI: 10.1016/j.net.2026.104144

Bub-Gyu Jeon , Sung-Wan Kim , Dong-Uk Park , Chae-Been Lee , DaeGi Hahm , Hong-Pyo Lee

{"title":"Seismic behavior of electrical cabinets with cast-in-place anchors: influence of concrete cracks and multi-bay installation","authors":"Bub-Gyu Jeon , Sung-Wan Kim , Dong-Uk Park , Chae-Been Lee , DaeGi Hahm , Hong-Pyo Lee","doi":"10.1016/j.net.2026.104144","DOIUrl":"10.1016/j.net.2026.104144","url":null,"abstract":"<div><div>Electrical cabinets are typically assembled in a multi-bay configuration, connecting two or more modules, and the structural implications of this setup must be carefully addressed. Concrete foundation cracks, often observed during field investigations at power plants, represent a common form of support deterioration. This study fabricated concrete foundations to simulate intact conditions and cracked conditions with 0.5 mm and 1.0 mm wide cracks at anchor locations. A simplified electrical cabinet model was constructed in single-bay, two-bay, and three-bay configurations and anchored to the concrete foundations using cast-in-place anchors to consider the effects of multi-bay configuration and support deterioration. Three-axis shaking table tests were conducted, including resonant frequency search and seismic fragility tests. The results indicated that cracks at the anchor locations can increase the uncertainty in the cabinet's resonant frequency. Specifically, when the concrete foundation was intact, seismic performance improved as the number of connected bays increased. However, cracks up to 1.0 mm in width degraded the seismic performance of multi-bay configurations but had a negligible impact on the single-bay cabinet. Moreover, distinct damage modes were observed between single-bay and multi-bay conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104144"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035814","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

Development of frictional pressure drop models for single- and two-phase flows in a helically coiled tube 螺旋管内单相和两相流动摩擦压降模型的建立

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-12 DOI: 10.1016/j.net.2026.104134

Oktari Zaidi, Byong Jo Yun, Jae Jun Jeong

{"title":"Development of frictional pressure drop models for single- and two-phase flows in a helically coiled tube","authors":"Oktari Zaidi, Byong Jo Yun, Jae Jun Jeong","doi":"10.1016/j.net.2026.104134","DOIUrl":"10.1016/j.net.2026.104134","url":null,"abstract":"<div><div>Helically coiled tubes (HCTs) are widely employed in small modular reactors (SMRs), due to their compact geometry and superior heat transfer performance. Accurate prediction of frictional pressure drop for single-phase and two-phase flows in HCTs is crucial for the design and safety analysis of SMRs. In this study, the characteristics of frictional pressure drop in HCTs were investigated using an experimental database comprising 1489 single-phase and 876 two-phase data points. A systematic physics-based model development framework was applied, including key parameters identification and statistically supported modeling to ensure the significance and independence of all selected parameters. Through this, dominant factors influencing frictional pressure drop in HCTs were determined. It was found that, in addition to the well-known flow variables, centrifugal force induced by main axial flow has a significant impact on pressure drop. Based on the finding, new empirical correlations were developed by explicitly incorporating a dimensionless centrifugal force number. The final formulation is designed to preserve asymptotic consistency with straight tube when the curvature effect vanishes. Assessment results indicate that the proposed correlations reduce the root mean square errors by 7.0 %, 9.1 %, and 15.0 %, respectively, compared to the best-performing existing models for single-phase laminar, single-phase turbulent, and two-phase flows.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104134"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035729","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

A variable universe fuzzy control method for the HCOTSG feedwater system of small pressurized water reactor 小型压水堆HCOTSG给水系统的变域模糊控制方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-05 DOI: 10.1016/j.net.2026.104116

Zhihui Yan , Xuan She , Shijia Yang , Wenjie Zeng , Zhifeng Li

{"title":"A variable universe fuzzy control method for the HCOTSG feedwater system of small pressurized water reactor","authors":"Zhihui Yan , Xuan She , Shijia Yang , Wenjie Zeng , Zhifeng Li","doi":"10.1016/j.net.2026.104116","DOIUrl":"10.1016/j.net.2026.104116","url":null,"abstract":"<div><div>Helical-Coil Once-Through Steam Generator (HCOTSG) is a key energy conversion component in the secondary circuit system of Small Pressurized Water Reactor (SPWR), exhibiting lower heat storage capacity and great difficulty in steam pressure regulation. The traditional fuzzy control method adopts a fixed domain of discourse, which has limited adaptability under load change conditions, and it is difficult to meet the requirements of HCOTSG for high precision control. Therefore, this paper proposes a variable universe fuzzy control (VUFC) method for the HCOTSG feedwater system, with the nonlinear mathematical model of the secondary circuit, the real-time adjustment domain of the scaling factor based on fuzzy rules is used to realize the online adaptive control of HCOTSG feedwater system. Simulation results of the SPWR under step load changes show that the VUFC offers faster response speed, smaller overshoot and stronger robustness than traditional fuzzy control, which mitigates the impacts of steam pressure on secondary circuit equipment and improves the operation safety of SPWR.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104116"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035723","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

Long-term corrosion behavior of a cold-spray copper-SiC composite coating for spent nuclear fuel disposal canisters 废核燃料处理罐用冷喷涂铜-碳化硅复合涂层的长期腐蚀行为

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-23 DOI: 10.1016/j.net.2026.104159

Minsoo Lee, Junhyuk Jang, Nakkyu Chae, Jin Seop Kim

{"title":"Long-term corrosion behavior of a cold-spray copper-SiC composite coating for spent nuclear fuel disposal canisters","authors":"Minsoo Lee, Junhyuk Jang, Nakkyu Chae, Jin Seop Kim","doi":"10.1016/j.net.2026.104159","DOIUrl":"10.1016/j.net.2026.104159","url":null,"abstract":"<div><div>A novel copper-silicon carbide (Cu-SiC) metal matrix composite (MMC) was fabricated using cold spray coating and evaluated as a corrosion-resistant barrier for spent nuclear fuel disposal canisters. The Cu-SiC MMC exhibited superior properties compared to pure copper, including reduced oxygen content and a more noble corrosion potential. To assess its long-term performance, a 3690-day corrosion test was conducted under simulated deep geological conditions at the KAERI Underground Research Tunnel (KURT), while embedded in Ca-type bentonite and exposed to 70 °C aerobic groundwater. After over a decade, the Cu-SiC MMC showed an average corrosion depth of only 4.02 ± 1.72 μm. The corrosion kinetics followed a distinct “S-shaped” pattern, attributed to long-term changes at the bentonite-copper interface. Post-test characterization, including surface profilometry and FIB-SEM analysis, confirmed that the chemically inert SiC particles effectively acted as a physical barrier, significantly reducing corrosion penetration. These findings demonstrate the excellent durability and corrosion resistance of Cu-SiC MMC, validating its potential for enhancing the long-term integrity of nuclear waste disposal canisters.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104159"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146090485","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

Enhancing quality control in radiography systems through automated algorithms 透过自动演算法，加强射线照相系统的品质控制

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-22 DOI: 10.1016/j.net.2026.104156

Herdi Firdaus Jamal , Mohammad Wasef Marashdeh , Muhammad Kabir Abdulkadir , Mohd Ilyas Sazali , Hanan Fawaz Akhdar , Muhamad Zabidi Ahmad , Mohd Zahri Abdul Aziz

{"title":"Enhancing quality control in radiography systems through automated algorithms","authors":"Herdi Firdaus Jamal , Mohammad Wasef Marashdeh , Muhammad Kabir Abdulkadir , Mohd Ilyas Sazali , Hanan Fawaz Akhdar , Muhamad Zabidi Ahmad , Mohd Zahri Abdul Aziz","doi":"10.1016/j.net.2026.104156","DOIUrl":"10.1016/j.net.2026.104156","url":null,"abstract":"<div><div>Quality control (QC) in radiography systems is essential for ensuring imaging accuracy and radiation safety. Traditional QC methods are time-consuming and prone to human error. Automated algorithms offer a potential solution by streamlining QC assessments. The aim of this study was to develop and evaluate the performance of an automated QC algorithm tailored for radiography systems in accordance with Malaysian regulatory requirements by comparing its efficiency, accuracy, and reliability against manual methods. QC algorithms were developed using Microsoft Excel for a comprehensive list of QC tests delineated by the Ministry of Health, Malaysia. These algorithms were designed to automate the input of measured data, execute necessary calculations, and deliver a pass/fail outcome based on established regulatory criteria. The performance of the algorithms was evaluated through data collected from 100 radiography machines across various locations and models. The study compared the time efficiency, accuracy and errors of algorithm-based QC assessments and manual calculations. The algorithm significantly (p < 0.001) reduced QC assessments time by 90 % and eliminated <strong>all</strong> calculation errors, outperforming manual assessments that occurred 64 times. <strong>This is the first Excel-based QC algorithm validated against Malaysian regulations, providing low-cost alternative to commercial systems.</strong></div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104156"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146090482","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

Tracking simulation of third-integer resonant extraction for Fermilab’s Mu2e experiment Fermilab Mu2e实验中第三整数共振提取的跟踪仿真

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2025-12-31 DOI: 10.1016/j.net.2025.104097

Chong Shik Park

引用次数: 0

Preliminary design and neutronic analyses of ECRH equatorial launcher toward CFEDR ECRH赤道发射装置的初步设计与中子分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2026-05-01 Epub Date: 2026-01-12 DOI: 10.1016/j.net.2026.104135

Chao Xu , Ming Gao , Yuanyuan Kuang , Dingzhen Li , Chao Zhang , Hanlin Wang , Nengtao Zhou , Shanliang Zheng , Yunying Tang , Xiaojie Wang

{"title":"Preliminary design and neutronic analyses of ECRH equatorial launcher toward CFEDR","authors":"Chao Xu , Ming Gao , Yuanyuan Kuang , Dingzhen Li , Chao Zhang , Hanlin Wang , Nengtao Zhou , Shanliang Zheng , Yunying Tang , Xiaojie Wang","doi":"10.1016/j.net.2026.104135","DOIUrl":"10.1016/j.net.2026.104135","url":null,"abstract":"<div><div>Electron Cyclotron Resonance Heating (ECRH) is one of the most important heating systems to maintain long pulse and high-power steady-state operation of fusion reactors. In the recent progress of the ECRH system for the China Fusion Engineering Demonstrator Reactor (CFEDR), the launcher must adopt a modular design while maintaining total mass below the limit for remote handling (RH) maintenance requirements. A drawer-type launcher in the fusion reactor environment has been designed. The equatorial launcher (EL) is composed of two main parts: shielding unit and optical unit containing drawer-type millimeter-wave transmission components. These units form a unified port plug structure. The nuclear analysis of the EL based on the preliminary design has been completed. While satisfying radiation shielding requirements, the optimal thickness of shielding components within the drawer is computationally determined to minimize the launcher's total mass. A double labyrinth shielding configuration is implemented at the gap between launcher and vacuum vessel, with simulation results demonstrating effective suppression of neutron streaming along the gap toward the rear launcher section. The radiation damage to various launcher components is quantified to provide critical data for the structural design and lifetime evaluation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104135"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035725","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