Nuclear Engineering and Technology最新文献_第8页

Long-term performance test of Cu canisters used for disposing of spent nuclear fuels under aerobic groundwater 在好氧地下水下处理乏核燃料用铜罐的长期性能试验

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-29 DOI: 10.1016/j.net.2025.103678

Junhyuk Jang , Minsoo Lee , Gha-Young Kim , Seok Yoon

{"title":"Long-term performance test of Cu canisters used for disposing of spent nuclear fuels under aerobic groundwater","authors":"Junhyuk Jang , Minsoo Lee , Gha-Young Kim , Seok Yoon","doi":"10.1016/j.net.2025.103678","DOIUrl":"10.1016/j.net.2025.103678","url":null,"abstract":"<div><div>Evaluating the long-term corrosion behavior of Cu under local groundwater is important for its use in fabricating disposal canisters. The long-term performance of KJ-I bentonite-embedded Cu disks was assessed for a testing period of 10 years. The results were compared with those obtained on MX-80 bentonite-embedded Cu disks. The disks retrieved from the MX-80 and KJ-I bentonites exhibited corrosion depths of 0.53 and 3.9 μm, respectively. The corrosion rate below 0.39 μm/year indicated that Ca-type KJ-I bentonite can also be used as a buffer material. The surface characterizations revealed the formation of a thin Cu oxide layer (∼0.5 μm) on the MX-80 bentonite-retrieved disk. A Cu<sub>2</sub>O layer (∼2 μm) was formed on the KJ-I bentonite-retrieved disk. During open-circuit potential measurements, the bentonite-embedded disk exhibited a potential below −125 mV, which is considerably lower than the pitting potential of Cu (∼250 mV), indicating that the occurrence of localized corrosion of Cu is largely reduced upon embedding in bentonite. This study demonstrates that KJ-I bentonite-embedded Cu canisters can be utilized for nuclear waste disposal under aerobic conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103678"},"PeriodicalIF":2.6,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143921848","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

Rapidly tracking the position of a radiation source using multiple radiation spectroscopy detectors with maximum likelihood position estimation 利用最大似然位置估计的多辐射光谱探测器快速跟踪辐射源的位置

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-29 DOI: 10.1016/j.net.2025.103671

Hyundong Kim , Seung-Jae Lee

{"title":"Rapidly tracking the position of a radiation source using multiple radiation spectroscopy detectors with maximum likelihood position estimation","authors":"Hyundong Kim , Seung-Jae Lee","doi":"10.1016/j.net.2025.103671","DOIUrl":"10.1016/j.net.2025.103671","url":null,"abstract":"<div><div>The location of a radiation source can be tracked by deriving the location from the number of measured radiation counts using multiple radiation spectroscopy detectors. However, this method we previously developed was found to produce errors as the area of radiation incident on the source and the radiation spectroscopy detector changed. In this study, a location tracking system using a radiation spectroscopy detector and maximum likelihood position estimation (MLPE) was developed to derive the exact location. The lookup table (LUT) of the MLPE was created through Geant4 Application of Tomographic Emission (GATE) simulation, and the experimental data were applied to the LUT created through simulation to estimate the location of the radiation source. As a result, the estimation was confirmed to be exceptionally accurate (97.07 ± 2.96 %). By applying the LUT created through simulation to the experiment, the LUT creation time was shortened and the convenience was improved. In addition, the measurement time could be shortened by using a radiation spectroscopy detector with excellent sensitivity as well as the ability to determine the location with excellent accuracy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103671"},"PeriodicalIF":2.6,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143881852","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 of system decontamination effectiveness by development of decontamination factor evaluation program 通过制定去污因素评价方案，分析系统去污效果

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-29 DOI: 10.1016/j.net.2025.103680

Jeseok Song, Chang-Lak Kim

引用次数: 0

Precision of moisture quantification in canisters during the vacuum desiccation process prior to the dry storage of spent nuclear fuel 乏核燃料干贮存前真空干燥过程中罐内水分定量的精度

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-28 DOI: 10.1016/j.net.2025.103674

Ji Hwan Lim, Kyoung-Sik Bang, Seung-Hwan Yu

{"title":"Precision of moisture quantification in canisters during the vacuum desiccation process prior to the dry storage of spent nuclear fuel","authors":"Ji Hwan Lim, Kyoung-Sik Bang, Seung-Hwan Yu","doi":"10.1016/j.net.2025.103674","DOIUrl":"10.1016/j.net.2025.103674","url":null,"abstract":"<div><div>This study investigates the complex interplay between canister volume and vacuum pump capacity during vacuum desiccation, revealing critical insights into optimizing drying processes. A high-capacity vacuum pump used with a small-volume canister can cause rapid energy extraction, potentially freezing moisture, while a low-capacity pump for a large-volume canister extends drying times. Through systematic lab-scale experiments, we found that higher pump capacities increase evaporation rates due to the latent heat consumption during water phase changes, especially evident during boiling due to enhanced surface area. Smaller canisters exhibited lower evaporation before and after boiling but surpassed larger canisters during boiling. Conversely, larger canisters faced delayed boiling and prolonged drying. A cross-analysis of residual moisture measuring tools—comparing initial errors over 10 % between precision mass balances and steam flow meters—achieved error reduction to 1.69 %–6.47 % by applying Magnus relative humidity equations and dew point data. Despite the steam flow meter's limitations in low humidity and high vacuum, these findings support refining and advancing drying technologies for residual moisture elimination in spent nuclear fuel canisters. Further research into quantification methodologies is recommended to ensure enhanced efficiency and reliability in practical applications of such systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103674"},"PeriodicalIF":2.6,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143921847","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 investigation on mixed convection in narrow rectangular channel under inclination condition 倾斜条件下窄矩形通道混合对流的数值研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-27 DOI: 10.1016/j.net.2025.103673

Qiang Lian , Lie Wei , Luteng Zhang , Simiao Tang , Longxiang Zhu , Zaiyong Ma , Wan Sun , Liangming Pan

{"title":"Numerical investigation on mixed convection in narrow rectangular channel under inclination condition","authors":"Qiang Lian , Lie Wei , Luteng Zhang , Simiao Tang , Longxiang Zhu , Zaiyong Ma , Wan Sun , Liangming Pan","doi":"10.1016/j.net.2025.103673","DOIUrl":"10.1016/j.net.2025.103673","url":null,"abstract":"<div><div>Narrow rectangular channels have been widely adopted in small modular reactors (SMRs), which show particular promise for maintaining stable driving forces under marine operating conditions. The flow and heat transfer characteristics of these channels are significantly affected by oceanic motions, particularly under low Reynolds number flow regimes. This study employs computational fluid dynamics (CFD) to model a 3 mm (gap) × 50 mm (width) × 1000 mm (length) channel for investigating mixed convection phenomena under various inclined conditions. Following rigorous mesh independence verification, the numerical framework is validated against both analytical solutions and experimental data from comparable rectangular channel configurations. The research mainly focuses on the coupled effects of thermodynamic instability and lateral forces on mixed convection dynamics in inclined narrow channels. The flow structure and temperature distribution on the cross-section are obtained under longitudinal inclination and transverse inclination. A comprehensive evaluation of mixed convection reveals that the onset of significant buoyancy effects can be characterized by a dimensionless criterion combining Richardson number, inclination angle, and normalized channel length. The critical value of <span><math><mrow><msup><mtext>Ri</mtext><mi>i</mi></msup><mi>z</mi><mo>/</mo><msub><mi>D</mi><mi>h</mi></msub></mrow></math></span> is determined as 0.45 under typical inclination conditions, beyond which buoyancy-driven secondary flows enhance thermal transport capacity compared to pure forced convection baselines.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103673"},"PeriodicalIF":2.6,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887751","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 investigation of the effect of operating conditions on internal flow behavior in APR1000 工况对APR1000内部流动特性影响的实验研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-27 DOI: 10.1016/j.net.2025.103669

Yo Han Kim, Kihwan Kim, Hae-Seob Choi, Hyosung Seol, Byung-Jun Lim, Woo-Shik Kim, Dong-Jin Euh

{"title":"Experimental investigation of the effect of operating conditions on internal flow behavior in APR1000","authors":"Yo Han Kim, Kihwan Kim, Hae-Seob Choi, Hyosung Seol, Byung-Jun Lim, Woo-Shik Kim, Dong-Jin Euh","doi":"10.1016/j.net.2025.103669","DOIUrl":"10.1016/j.net.2025.103669","url":null,"abstract":"<div><div>Understanding the behavior of the primary coolant in a nuclear reactor is crucial for evaluating thermal margins and ensuring reactor safety. This study examines the behavior of the primary coolant using the ACOP experimental facility, a 1/5 scale model of the APR1000 reactor, to evaluate the effects of flow rate and flow unbalance on coolant distribution. Experiments were performed at flow rates of 60 %, 80 %, 100 %, and 110 % under balanced conditions, as well as under 15 % unbalanced and extreme unbalanced conditions with three pumps. The coolant flow characteristics were assessed by measuring the core inlet flow distribution, core outlet pressure, upper plenum pressure, and hot leg velocity using 177 core simulators. The results showed that the core inlet flow distribution ranged between 88 % and 112 % across all conditions. Under extreme unbalanced conditions, a maximum deviation of 5.3 % in single core flow distribution was observed. The outlet pressure distribution remained stable under four-pump conditions but showed greater variation with three pumps. The study concludes that coolant flow rate and flow unbalance had minimal impact under balanced four-pump conditions, while significant effects on outlet pressure, upper plenum pressure, and hot leg velocity were evident under extreme unbalanced conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103669"},"PeriodicalIF":2.6,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143891430","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 of hardening strategies based on the single event effect induced by atmospheric-like neutrons 基于类大气中子诱导的单事件效应的硬化策略研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-25 DOI: 10.1016/j.net.2025.103666

Ze-Qi Huang , Han-Tao Jing , Li-Hua Mo , Zhi-Liang Hu , Gao-Peng Shen , Zhi-Hao Zhou , Chang Cai

引用次数: 0

Transient CFD analysis of MSRE fuel drain tank MSRE燃油箱瞬态CFD分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-24 DOI: 10.1016/j.net.2025.103659

Moon Hyeok Kang, Jeong Ik Lee

{"title":"Transient CFD analysis of MSRE fuel drain tank","authors":"Moon Hyeok Kang, Jeong Ik Lee","doi":"10.1016/j.net.2025.103659","DOIUrl":"10.1016/j.net.2025.103659","url":null,"abstract":"<div><div>The Molten Salt Reactor (MSR) is one of the Generation IV reactors and it provides inherent safety and high efficiency. The Fuel Drain Tank (FDT) is a critical component in MSR for storing fuel salt in case of shutdown as well as emergency and has to be designed to remove decay heat reliably for long time. To design and predict the behavior of MSR FDT, the Oak Ridge National Lab (ORNL) assumed certain parameters in 1960s while designing the Molten Salt Reactor Experiment (MSRE). One of the key assumptions is the difference between the mixed-mean temperature of the fuel salt and the thimble tube surface temperature remains constant at 25 F. This assumption greatly simplifies the heat removal prediction as well as the design of FDT. However, the assumption was not revisited for verification in the open literature. Thus, this study attempted to verify the value using the three-dimensional transient CFD simulations which were verified through the hierarchical verification and validation methodology. Consequently, it was found that the difference between FDT mixed-mean temperature and thimble tube surface-averaged temperature was maintained around 20 K, not 25 F after thermal stratification was well-developed.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103659"},"PeriodicalIF":2.6,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887750","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

Effect of bending on the geometry and collapse pressure of helical steam generator tubes: Numerical study 弯曲对螺旋蒸汽发生器管的几何形状和坍塌压力的影响：数值研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-24 DOI: 10.1016/j.net.2025.103657

M. Park , M.W. Lee , K. Ahn , G.G. Youn

{"title":"Effect of bending on the geometry and collapse pressure of helical steam generator tubes: Numerical study","authors":"M. Park , M.W. Lee , K. Ahn , G.G. Youn","doi":"10.1016/j.net.2025.103657","DOIUrl":"10.1016/j.net.2025.103657","url":null,"abstract":"<div><div>This study investigates the effects of bending processes on the geometry and collapse pressure of helical steam generator tubes used in Small Modular Reactors (SMRs). The bending process induces geometric imperfections such as ovality and eccentricity, as well as work hardening, which significantly impact the structural integrity of the tubes. Finite element analysis, employing an implicit numerical scheme, was used to simulate the multi-roller bending process, considering three different curvature radii and varying tube thicknesses. The results indicate that thicker tubes exhibit higher eccentricity, while thinner tubes show increased ovality. Additionally, the collapse pressure was found to increase with tube thickness and the degree of plastic deformation. By applying an implicit finite element scheme to simulate the multi-roller bending process, this study captures realistic geometric imperfections and work hardening effects that are often overlooked in prior studies. These findings contribute to improving the accuracy and reliability of the design and manufacturing of helical steam generator tubes in nuclear reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103657"},"PeriodicalIF":2.6,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887745","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

Evaluation of the activity levels and the radiological hazards associated with the imported chemical and local organic fertilizers used in Ethiopia 评估与埃塞俄比亚使用的进口化学肥料和当地有机肥料有关的活动水平和辐射危害

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-24 DOI: 10.1016/j.net.2025.103655

Alelign Worku Gedefaw, Tilahun Tesfaye Deressu

{"title":"Evaluation of the activity levels and the radiological hazards associated with the imported chemical and local organic fertilizers used in Ethiopia","authors":"Alelign Worku Gedefaw, Tilahun Tesfaye Deressu","doi":"10.1016/j.net.2025.103655","DOIUrl":"10.1016/j.net.2025.103655","url":null,"abstract":"<div><div>In this study, the activity concentrations of <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K in fertilizer samples obtained from farmers and suppliers utilized in Ethiopia were measured using gamma-ray spectrometry with an HPGe detector. The highest average activity concentrations of <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K were found as 45.8 ± 3.1 in nitrogen phosphorous compound (NP) fertilizers, 25.7 ± 3.0 in organic fertilizers, and 799.5 ± 64.9 in organic fertilizers Bq/kg, respectively, and the corresponding lowest average values were found as 17.4 ± 2.4 in organic fertilizers, 14.3 ± 1.8 in urea, and 135.1 ± 6.6 in urea Bq/kg, respectively. The average activity concentrations of <sup>226</sup>Ra in NP fertilizers and <sup>40</sup>K in animal fertilizers were higher than the Earth's crust average values of 32 and 412 Bq/kg for <sup>226</sup>Ra, and <sup>40</sup>K respectively. Radiological hazard indicator parameters, such as the radium equivalent activity (Ra<sub>eq</sub>), outdoor absorbed dose rates (<em>D</em><sub>out</sub>), outdoor annual effective doses (AED<sub>out</sub>), outdoor excess lifetime cancer risk (ELCR<sub>out</sub>), external hazard index (H<sub>ex</sub>), internal hazard index (H<sub>in</sub>), alpha index (<em>I</em><sub>α</sub>), and annual gonadal dose equivalent (AGDE), were estimated in both chemical and organic fertilizer samples. The resulting average values were within the range of the international dose safety limit of fertilizers.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103655"},"PeriodicalIF":2.6,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143922856","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