Nuclear Engineering and Technology最新文献_第8页

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

Nonlinear structural analysis for structural integrity re-evaluation of existing spent fuel pool in nuclear power plant under beyond design basis earthquake 非设计基础地震作用下核电厂既有乏燃料池结构完整性再评价的非线性结构分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-31 DOI: 10.1016/j.net.2025.103723

Ting-Yu Fan, Chin-Yu Lin, Hsoung-Wei Chou

{"title":"Nonlinear structural analysis for structural integrity re-evaluation of existing spent fuel pool in nuclear power plant under beyond design basis earthquake","authors":"Ting-Yu Fan, Chin-Yu Lin, Hsoung-Wei Chou","doi":"10.1016/j.net.2025.103723","DOIUrl":"10.1016/j.net.2025.103723","url":null,"abstract":"<div><div>This paper presents reevaluation of structural integrity for an existing spent fuel pool (SFP) of the pressurized water reactor power plant in Taiwan, as well as to investigate the locations of potential weaknesses in the whole structure under beyond design basis earthquake (BDBE). In addition, the partial cracking effect from BDBE was also considered in this study associated with higher damping ratio and reduced flexural rigidity. At first, the analysis procedure for single wall based on the structural analysis standards and equivalent seismic load assessment introduced in EPRI-3002009564 and ACI 350.3–06 was considered. All structural crucial aspects considered relevant were included in the analyses: the concrete structure, the steel liner, its connections and the containing fluid. Then, evaluations considering more detailed SFP structure and comprehensive loading combinations were conducted and compared. The analyses results reveal that the structural responses raise significantly when considering increasing the damping ratio and reducing the rigidity of the structure. Furthermore, it is found that the most severely damaged location in the SFP structure is on the south wall, because lateral force on the south wall is larger than others. However, even in this case, the steel liner can still maintain the structural integrity under BDBE.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103723"},"PeriodicalIF":2.6,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144263784","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

Path planning of RRT* algorithm with subregional dynamic probabilistic sampling based on artificial potential field in radiation environments 辐射环境下基于人工势场的分区域动态概率抽样RRT*算法路径规划

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-31 DOI: 10.1016/j.net.2025.103706

Yanjun Wang, Jinjia Cao, Xiaochang Zheng, Yulong Zhang, Yadong Zhang, Wei Chen

{"title":"Path planning of RRT* algorithm with subregional dynamic probabilistic sampling based on artificial potential field in radiation environments","authors":"Yanjun Wang, Jinjia Cao, Xiaochang Zheng, Yulong Zhang, Yadong Zhang, Wei Chen","doi":"10.1016/j.net.2025.103706","DOIUrl":"10.1016/j.net.2025.103706","url":null,"abstract":"<div><div>An improved path planning method, ASD-RRT*, is proposed to address the path planning problem in complex static radiation environments. First, the artificial potential field (APF) method is introduced to optimize the RRT* algorithm, guiding the RRT* tree nodes to shift away from the radiation sources. Next, a subregional dynamic probabilistic sampling strategy is employed, improving the goal-directedness of the path search process while considering the effects of radiation dose. Finally, the Douglas-Peucker algorithm is used to smooth the path. This study builds radiation fields using Geant4, simulates multiple radiation scenarios, and performs path planning using A*, PRM, APF-PRM, RRT*, and ASD-RRT* algorithms. The research results indicate that the ASD-RRT* algorithm performs better in navigating narrow regions and excels in complex radiation environments. It can find a safer path with the lowest cumulative dose within a reasonable time, providing a reference solution for path planning in radiation field environments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103706"},"PeriodicalIF":2.6,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177822","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 theoretical approach to understand the reaction dynamics for producing Technetium isotopes 了解生产锝同位素的反应动力学的理论方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-30 DOI: 10.1016/j.net.2025.103672

Amit Chauhan

引用次数: 0

A historical review of high heat flux cooling techniques 高热流密度冷却技术的历史回顾

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-30 DOI: 10.1016/j.net.2025.103725

Ji Hwan Lim, Seung-Hwan Yu

{"title":"A historical review of high heat flux cooling techniques","authors":"Ji Hwan Lim, Seung-Hwan Yu","doi":"10.1016/j.net.2025.103725","DOIUrl":"10.1016/j.net.2025.103725","url":null,"abstract":"<div><div>This review provides a comprehensive historical analysis of high heat flux cooling techniques critical for advanced applications in nuclear energy, aerospace propulsion, and high-performance electronics. We trace the evolution of cooling strategies from early nucleate boiling experiments to recent innovations such as swirl flow devices, Hypervapotron channels, screw tubes, and porous coatings. By synthesizing experimental results and theoretical models, we identify significant enhancements in critical heat flux (CHF) and heat transfer coefficients, with swirl flow techniques offering improvements of 50–100 % over smooth channels and Hypervapotron systems achieving CHF levels up to 30 MW/m<sup>2</sup> under optimal conditions. Our review also highlights that while individual cooling methods exhibit unique performance benefits, an integrated hybrid approach holds promise for future high heat flux cooling systems. However, the translation from laboratory-scale success to practical, industrial-scale applications presents challenges, particularly in system complexity, maintenance, and cost analysis. We conclude that future research must bridge these gaps through interdisciplinary strategies, robust cost-analysis frameworks, and optimization studies. This balanced evaluation underscores both the technical achievements and the practical hurdles that define the current state and future potential of high heat flux cooling technologies.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103725"},"PeriodicalIF":2.6,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144222531","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

Measurement of IBD-like background with plastic scintillator detector array at surface level 表面塑料闪烁体探测器阵列测量类ibd背景

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-30 DOI: 10.1016/j.net.2025.103707

Chao Wang , Gao-Kui He , Hua-Yang Tian , Xiu-Zhang Tang , Jiang-Bin Zhao , Yang Liu , Chun-Yu Gao

引用次数: 0

Reactor physics fast calculation method based on model order reduction and machine learning 基于模型阶数约简和机器学习的反应堆物理快速计算方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-30 DOI: 10.1016/j.net.2025.103724

Chen Zhao , Qinyi Zhang , Bin Zhang , Jiangyu Wang , Jiayi Liu , Lianjie Wang , Bangyang Xia , Xiaoming Chai , Xingjie Peng

{"title":"Reactor physics fast calculation method based on model order reduction and machine learning","authors":"Chen Zhao , Qinyi Zhang , Bin Zhang , Jiangyu Wang , Jiayi Liu , Lianjie Wang , Bangyang Xia , Xiaoming Chai , Xingjie Peng","doi":"10.1016/j.net.2025.103724","DOIUrl":"10.1016/j.net.2025.103724","url":null,"abstract":"<div><div>The rapid development of artificial intelligence technology has provided new ideas and methods for reactor physics calculations. Based on AI technology, a fast calculation method for reactor physics has been established, which combines model order reduction and machine learning to address the challenges of excessive parameter quantities in machine learning-based parameter prediction. During the training process, the full-order model is established using the two-step core nuclear design software package TORCH, and the model order reduction theory is applied, which are then trained using the random forest machine learning method. In the prediction process, the basis weight coefficients are rapidly calculated for specific input parameters, and the core distribution results are reconstructed. A reactor physics fast calculation program has been developed and verified using a M310-type pressurized water reactor nuclear power plant with 9522 samples. All results show that the fast calculation method based on model order reduction and machine learning has good computational efficiency and accuracy. The calculation time can be reduced to 0.1 s and the proportion of samples with less than 1 % deviation in various core physics parameters is higher than 90 %.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103724"},"PeriodicalIF":2.6,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271357","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

The effect of storage conditions and computer model simplification on the thermal state of the RBMK-1500M2 cask 储存条件和计算机模型简化对RBMK-1500M2木桶热状态的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-29 DOI: 10.1016/j.net.2025.103729

Kęstutis Račkaitis , Povilas Poškas , Robertas Poškas , Hussam Jouhara

{"title":"The effect of storage conditions and computer model simplification on the thermal state of the RBMK-1500M2 cask","authors":"Kęstutis Račkaitis , Povilas Poškas , Robertas Poškas , Hussam Jouhara","doi":"10.1016/j.net.2025.103729","DOIUrl":"10.1016/j.net.2025.103729","url":null,"abstract":"<div><div>Interim storage of spent nuclear fuel is a very important part of the overall nuclear power generation cycle. At Ignalina NPP, spent nuclear fuel is stored in interim storage facilities in specially designed casks before being transferred to a geological repository. The internal structure of spent nuclear fuel casks and the processes involved are quite complex. Therefore, simplifying and optimizing simulations for evaluating decay heat removal from the cask is worthwhile. In this paper, the effect of computer model simplifications on the thermal characteristics of the CONSTOR RBMK-1500/M2 cask stored in building-type and open-type storage facilities is presented. The modeling was carried out using the ANSYS Fluent code. The analysis showed a substantial impact of solar insolation. Also, in the case of the homogenization of the SNF load in the basket, higher temperatures are obtained compared with the case when detailed modeling of the internal basket structure is performed. Hence, it was demonstrated that the homogenization model can be used in safety assessment as a conservative approach for the modeling of decay heat removal from the cask.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103729"},"PeriodicalIF":2.6,"publicationDate":"2025-05-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144263782","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

Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel 对高放射性三结构各向同性核燃料进行x射线计算机断层扫描的安全策略

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-28 DOI: 10.1016/j.net.2025.103726

William Chuirazzi , Jayson Bush , Brian Gross , Matthew Bryant , Ken Clark , Miles Cook , Joshua Burtenshaw , Joseph Price , Swapnil Morankar , McKenzie Blattner , Raegan Landon , Keth Galloway , Justin Stanger , Ruger Stamos , Justin Duke , Camren Watt , John Stempien

{"title":"Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel","authors":"William Chuirazzi , Jayson Bush , Brian Gross , Matthew Bryant , Ken Clark , Miles Cook , Joshua Burtenshaw , Joseph Price , Swapnil Morankar , McKenzie Blattner , Raegan Landon , Keth Galloway , Justin Stanger , Ruger Stamos , Justin Duke , Camren Watt , John Stempien","doi":"10.1016/j.net.2025.103726","DOIUrl":"10.1016/j.net.2025.103726","url":null,"abstract":"<div><div>Nondestructive post-irradiation examination of nuclear fuels and materials is useful in collecting data to inform commercial licensing of new nuclear concepts. This work details the planning, shielding design, and workflow of an X-ray computed tomography examination of an irradiated AGR-5/6/7 tristructural isotropic fuel compact with a dose rate of 1318 R/h on contact from both β and ɤ-ray radiation with 120 R/h of the dose rate coming exclusively from ɤ-rays. Rather than waiting for radioactive decay to reduce the dose rate from the sample, careful implementation of specially developed shielding and work controls enabled some examinations of the irradiated fuel in a timelier manner, which benefits the ongoing qualification and commercialization cases for this fuel by reducing the timeline from irradiated to examination. This timeframe reduction is important as data from these experiments can be more quickly available to inform modeling efforts and subsequent experiments. While this work represents the hottest radiological sample that has been openly transported and examined at Idaho National Laboratory's Irradiated Materials Characterization Laboratory to date, it is anticipated that this work and its lessons learned will facilitate future examinations of similar or even more radioactive specimens.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103726"},"PeriodicalIF":2.6,"publicationDate":"2025-05-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184974","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

Sorption of U(IV) on MX-80, illite, shale and limestone in Na-Ca-Cl solutions 在Na-Ca-Cl溶液中，MX-80、伊利石、页岩和石灰岩对U（IV）的吸附

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-28 DOI: 10.1016/j.net.2025.103720

Shinya Nagasaki , Zhiwei Zheng , Jianan Liu , Jieci Yang , Tianxiao Tammy Yang

{"title":"Sorption of U(IV) on MX-80, illite, shale and limestone in Na-Ca-Cl solutions","authors":"Shinya Nagasaki , Zhiwei Zheng , Jianan Liu , Jieci Yang , Tianxiao Tammy Yang","doi":"10.1016/j.net.2025.103720","DOIUrl":"10.1016/j.net.2025.103720","url":null,"abstract":"<div><div>Uranium has been identified as an element of interest for the safety assessment of a deep geological repository (DGR) for used nuclear fuel. This paper studied the sorption of tetravalent U(IV) onto MX-80 bentonite, illite, shale and limestone in ionic strength 0.1–6 mol/kgw (m) Na-Ca-Cl solutions at pH<sub>m</sub> = 4–10 (for MX-80, illite, shale) and pH<sub>m</sub> = 5–10 (for limestone) under reducing conditions. Sorption of U(IV) on MX-80 increased with pH<sub>m</sub> until pH<sub>m</sub> = 8 and then reached a sorption plateau. Sorption of U(IV) on illite and shale increased from pH<sub>m</sub> = 4 to 5 and then reached a sorption plateau. Sorption of U(IV) on limestone increased with pH<sub>m</sub> up to pH<sub>m</sub> = 7 and then steeply decreased with pH<sub>m</sub>. Sorption of U(IV) on all four solids was not influenced by the ionic strength of Na-Ca-Cl solutions. The sorption of U(IV) onto MX-80 and illite in Na-Ca-Cl solutions was successfully simulated by a 2 site protolysis non-electrostatic surface complexation and cation exchange (2SPNE SC/CE) model using three inner-sphere surface complexation reactions. Values of surface complexation constants (log <em>K</em><sup>0</sup>) were optimized.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103720"},"PeriodicalIF":2.6,"publicationDate":"2025-05-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144263783","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