Nuclear Engineering and Technology最新文献_第6页

Food surface radiation sterilization 食品表面辐射灭菌

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-13 DOI: 10.1016/j.net.2025.103690

S.Yu. Sokovnin

引用次数: 0

Design characteristics of nuclear steam supply system and passive safety system for Innovative Small Modular Reactor (i-SMR) 新型小型模块化反应堆（i-SMR）核供汽系统及被动安全系统设计特点

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-12 DOI: 10.1016/j.net.2025.103697

Sang Gyu Lim, Hyun Suk Nam, Do Hwan Lee, Sang Won Lee

{"title":"Design characteristics of nuclear steam supply system and passive safety system for Innovative Small Modular Reactor (i-SMR)","authors":"Sang Gyu Lim, Hyun Suk Nam, Do Hwan Lee, Sang Won Lee","doi":"10.1016/j.net.2025.103697","DOIUrl":"10.1016/j.net.2025.103697","url":null,"abstract":"<div><div>In response to the growing global climate crisis, nuclear power, particularly through small modular reactors (SMRs), is emerging as a potential solution for sustainable energy production. This paper presents an innovative SMR (i-SMR) design being developed in the Republic of Korea, which integrates proven technologies from existing pressurized water reactors while emphasizing enhanced safety, cost-effectiveness, and operational flexibility. The i-SMR features a fully passive safety system, achieving a core damage frequency of 1E-9, thus significantly reducing the necessity for public evacuation during potential accidents. The i-SMR design incorporates several key elements, including a boron-free operation, a helical coil steam generator, an in-vessel control rod drive mechanism, and a canned-motor reactor coolant pump within an integrated nuclear steam supply system. This paper explores the design characteristics and the detailed operating mechanism of the passive safety system, comprising the passive emergency core cooling system, passive auxiliary feedwater system, and passive containment cooling system. Safety performance analyses were conducted for a loss-of-coolant accident using the Multi-dimensional Analysis of Reactor Safety (MARS) code. The analysis results demonstrate the performance and the thermal-hydraulic behavior of the passive safety system with key phenomena affecting the performance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103697"},"PeriodicalIF":2.6,"publicationDate":"2025-05-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184976","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

Bentonite as an engineered barrier material for nuclear waste repository - Geotechnical perspectives, key properties, knowledge gaps, and opportunities 膨润土作为核废料储存库的工程屏障材料-岩土工程观点，关键特性，知识差距和机会

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-12 DOI: 10.1016/j.net.2025.103700

Dong-Hwa Noh , Seunghee Kim , Jose Maria Ferdinand Victoria Calaunan , Yuan Feng , Jongwan Eun , Yong-Rak Kim

{"title":"Bentonite as an engineered barrier material for nuclear waste repository - Geotechnical perspectives, key properties, knowledge gaps, and opportunities","authors":"Dong-Hwa Noh , Seunghee Kim , Jose Maria Ferdinand Victoria Calaunan , Yuan Feng , Jongwan Eun , Yong-Rak Kim","doi":"10.1016/j.net.2025.103700","DOIUrl":"10.1016/j.net.2025.103700","url":null,"abstract":"<div><div>The deep geological repository is a widely recognized solution for isolating high-level radioactive waste (HLW). Bentonite, with its low hydraulic permeability, high swelling property, and strong sorption capacity, serves as a key engineered barrier material to prevent radioactive leakage. While extensive studies have examined its thermo-hydro-mechanical (THM) properties, some aspects still remain unclear, requiring further research to secure the long-term stability of bentonite. This paper presents a comprehensive review of bentonite's role in deep geological repositories from a geotechnical perspective. It first review the basics of montmorillonite, the primary mineral of bentonite, and its unique pore structure. Next, it examines past and ongoing nuclear waste disposal projects worldwide, highlighting key findings. Furthermore, the essential engineering properties of compacted bentonite blocks, including thermal and hydraulic conductivity, swelling pressure, water retention capacity, and mineral transformation, are reviewed. Lastly, this paper discusses the challenges, opportunities, and future research needs for optimizing bentonite's performance as a barrier material in geological disposal systems. By consolidating past research and identifying knowledge gaps, this review aims to provide insights into improving the long-term efficiency and stability of bentonite-based barrier systems for HLW containment.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103700"},"PeriodicalIF":2.6,"publicationDate":"2025-05-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144106747","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 and design of high-reliability magnet power supply architecture for CiADS CiADS高可靠性磁体电源结构的研究与设计

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-10 DOI: 10.1016/j.net.2025.103692

Wenqi Lyu , Yuan He , Ximeng Chen , Zhongzu Zhou , Zhijun Wang , Jiang Zhao

{"title":"Research and design of high-reliability magnet power supply architecture for CiADS","authors":"Wenqi Lyu , Yuan He , Ximeng Chen , Zhongzu Zhou , Zhijun Wang , Jiang Zhao","doi":"10.1016/j.net.2025.103692","DOIUrl":"10.1016/j.net.2025.103692","url":null,"abstract":"<div><div>The China Initiative Accelerator Driven System (CiADS) is a major national scientific infrastructure project managed by the Institute of Modern Physics, Chinese Academy of Sciences. It comprises a superconducting linear accelerator, a high-power spallation target, and a subcritical reactor. Once completed, it will be the world's first megawatt-level accelerator-driven subcritical system proof-of-concept device. As a critical component of the superconducting linear accelerator, the magnet power supply system plays a key role in the reliable operation of the accelerator. In this paper, based on the high reliability requirements of CiADS magnet power supply system, the functional composition and failure modes of magnet power supply system are sorted out and analyzed, and a Bayesian network model based on fault tree is established, and the model is optimized. Through analyzing the optimized fault model, a new architecture for the magnet power supply system is proposed and evaluated via Monte Carlo simulations for reliability. The results indicate that the new architecture enhances the reliability of the power supply system, confirming its rationality and feasibility.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103692"},"PeriodicalIF":2.6,"publicationDate":"2025-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143947972","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

Fractional Scaling Analysis - Methodology application to LSTF facility and a PWR for a small break LOCA transient 分数标度分析方法在LSTF设施和压水堆上的应用

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-10 DOI: 10.1016/j.net.2025.103696

César Berna-Escriche , David Blanco , José Luis Muñoz-Cobo , Lucas Álvarez-Piñeiro , Alberto Escrivá

{"title":"Fractional Scaling Analysis - Methodology application to LSTF facility and a PWR for a small break LOCA transient","authors":"César Berna-Escriche , David Blanco , José Luis Muñoz-Cobo , Lucas Álvarez-Piñeiro , Alberto Escrivá","doi":"10.1016/j.net.2025.103696","DOIUrl":"10.1016/j.net.2025.103696","url":null,"abstract":"<div><div>Scaling methodologies quantitatively assess the behavioral differences between small-scale experimental systems and full-size commercial plants during specific accidental scenarios. These methods guide the design and operation of experimental facilities to reliably replicate larger systems, ensuring safety systems are developed and accident sequences predicted accurately. Early integration of scaling calculations into the experimental design phase allows for reliable extrapolation of results to commercial plants. This study applied Fractional Scaling Analysis (FSA) to compare a scaled LSTF experimental facility and a full-size Siemens-KWU reactor during a Small Break LOCA in the hot leg (ROSA 1.2 test). The transient was divided into five phases, each analyzed for thermal-hydraulic similarity. Despite minor scaling distortions, the results showed strong consistency in pressure and level evolution, confirming good scalability between the facilities for this scenario. FSA demonstrated its versatility, allowing data from one type of facility (e.g., Westinghouse-type) to inform analyses for plants of a different type (e.g., Siemens-KWU). A new method provided a \"normalized scalability\" metric for the entire transient, with figures of merit for pressure and level reaching ∼0.3 (far below 1), indicating good scalability. Non-conservative distortions were minimal (<0.16), enabling quantitative comparisons across plants and transients for enhanced safety and design validation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103696"},"PeriodicalIF":2.6,"publicationDate":"2025-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144069156","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

Uncertainty analysis based on Bayesian inference for partial defect verification of PWR spent nuclear fuel 基于贝叶斯推理的压水堆乏燃料部分缺陷验证的不确定性分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-10 DOI: 10.1016/j.net.2025.103679

Hojik Kim , Hyung-Joo Choi , Woojin Kim , Seungmin Lee , Chul Hee Min , Sung-Woo Kwak

引用次数: 0

Experimental evaluation of irradiation capsule design efficiency for molybdenum-99 production 钼-99生产辐照胶囊设计效率的实验评价

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-09 DOI: 10.1016/j.net.2025.103694

D.S. Sairanbayev, M.T. Aitkulov, Sh.Kh. Gizatulin, A.N. Gurin, Ye.T. Chakrova, K.S. Kisselyov, A. Ch Ashibayev, A.A. Shaimerdenov

{"title":"Experimental evaluation of irradiation capsule design efficiency for molybdenum-99 production","authors":"D.S. Sairanbayev, M.T. Aitkulov, Sh.Kh. Gizatulin, A.N. Gurin, Ye.T. Chakrova, K.S. Kisselyov, A. Ch Ashibayev, A.A. Shaimerdenov","doi":"10.1016/j.net.2025.103694","DOIUrl":"10.1016/j.net.2025.103694","url":null,"abstract":"<div><div>Currently, technetium-99m is widely used in nuclear diagnostic medicine and is obtained from molybdenum-99. In Kazakhstan, the technology for producing <sup>99</sup>Mo/<sup>99m</sup>Tc generators to obtain a radiopharmaceutical was developed and introduced into serial production. Molybdenum-99 is produced via thermal neutron irradiation of molybdenum powder in a WWR-K reactor. However, in this case, the maximum specific activity generated is proportional to the cross-section of the radiation capture of a thermal neutron by the molybdenum-98 nucleus (0.13 b). In contrast, the epithermal neutron region offers higher cross-section resonances (6.9 b), suggesting potential for increased specific activity, which extends the generator operating time and improves its competitiveness. Based on this, an improved irradiation capsule design was developed to produce molybdenum-99 in a WWR-K reactor. The neutron characteristics of an irradiation capsule in the reactor core of a critical facility were also studied. This paper presents the results of experimental studies and demonstrates the effect of the irradiation capsule design on the energy distribution of neutrons. The possibility of increasing the specific activity of molybdenum-99 by 10 % when irradiating molybdenum with a natural isotopic composition and by 23 % when using molybdenum enriched to 98.6 % was demonstrated.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103694"},"PeriodicalIF":2.6,"publicationDate":"2025-05-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144069154","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 modeling and wind tunnel experimental study of pollutant dispersion in coastal continent 沿海大陆污染物扩散的数值模拟与风洞试验研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-09 DOI: 10.1016/j.net.2025.103693

Meng-yu Yao , Zhi-xiang Liu , Pei-lin Xiao , Dong Xie

{"title":"Numerical modeling and wind tunnel experimental study of pollutant dispersion in coastal continent","authors":"Meng-yu Yao , Zhi-xiang Liu , Pei-lin Xiao , Dong Xie","doi":"10.1016/j.net.2025.103693","DOIUrl":"10.1016/j.net.2025.103693","url":null,"abstract":"<div><div>Coastal areas are preferred for nuclear power plants due to the availability of seawater for cooling. However, siting also requires evaluating radiation doses to the environment and public during normal operation and potential accidents. This study examines how thermal differences and coastal meteorological conditions affect pollutant dispersion, using a three-dimensional numerical model of the flow field validated against wind tunnel experiments at a nuclear power plant. The validation shows less than 15 % error between simulations and experiments. Computational fluid dynamics (CFD) simulations were conducted under varying sea and land temperatures and wind speeds to analyze flow field structures and pollutant dispersion. Results reveal that the thermal internal boundary layer significantly influences pollutant dispersion. Higher wind speeds reduce the effect of temperature on flow field structure, while thermal variations affect vertical pollutant dispersion. The effective dose estimation model calculates a maximum downwind dose rate of 1.28mSv/year, well below the International Commission on Radiological Protection's annual dose limit. These findings offer insights into minimizing environmental risks and ensuring safety at coastal nuclear power plants.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103693"},"PeriodicalIF":2.6,"publicationDate":"2025-05-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144089775","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

In-depth understanding of sodium heat transfer characteristics with low Prandtl number in wire-wrapped fuel assemblies using high-fidelity CFD technique 利用高保真CFD技术深入了解低普朗特数线包燃料组件中钠的传热特性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-08 DOI: 10.1016/j.net.2025.103686

Jophous Mugabi , Hanseop Song , Jae-Ho Jeong

{"title":"In-depth understanding of sodium heat transfer characteristics with low Prandtl number in wire-wrapped fuel assemblies using high-fidelity CFD technique","authors":"Jophous Mugabi , Hanseop Song , Jae-Ho Jeong","doi":"10.1016/j.net.2025.103686","DOIUrl":"10.1016/j.net.2025.103686","url":null,"abstract":"<div><div>Understanding the thermal-hydraulic behavior of sodium-cooled fast reactors is crucial for optimizing their performance and safety. This study investigates the unique low Prandtl number properties of liquid sodium coolant, which influence heat transfer and fluid dynamics in turbulent flows within wire-wrapped fuel bundles. Using a combination of experimental data and high-fidelity Computational Fluid Dynamics (CFD) simulations, we analyzed key thermal-hydraulic characteristics for the ORNL 19-pin, Toshiba 37-pin, WARD 61-pin, and KAERI 61-pin fuel bundles under various heating and flow conditions. CFD simulations were conducted in STAR-CCM+ and ANSYS CFX and examined mass flow rates, pressure drops, and temperature distributions, validated against experimental data. Sensitivity analyses of turbulence models (SST, k-ε, and k-ω) indicated that the SST model best captured complex flow and three-dimensional vortical structures in SFR conditions, with edge subchannels exhibiting enhanced heat transfer due to higher axial velocities. Code-to-code comparisons confirmed strong agreement in predicted results, with STAR-CCM + aligning more closely with experimental data in some cases. The study underscores the importance of advanced CFD techniques in accurately modeling thermal management in wire-wrapped fuel bundles, contributing to improved safety and efficiency in SFR systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103686"},"PeriodicalIF":2.6,"publicationDate":"2025-05-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144222438","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

Impact of varying Bi2O3 content on physical, mechanical, structural and gamma ray shielding properties of Bi2O3-B2O3-SiO2-Na2O glass system 不同Bi2O3含量对Bi2O3- b2o3 - sio2 - na2o玻璃体系物理、机械、结构和γ射线屏蔽性能的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-08 DOI: 10.1016/j.net.2025.103684

Aljawhara H. Almuqrin , M.I. Sayyed , Ashok Kumar

{"title":"Impact of varying Bi2O3 content on physical, mechanical, structural and gamma ray shielding properties of Bi2O3-B2O3-SiO2-Na2O glass system","authors":"Aljawhara H. Almuqrin , M.I. Sayyed , Ashok Kumar","doi":"10.1016/j.net.2025.103684","DOIUrl":"10.1016/j.net.2025.103684","url":null,"abstract":"<div><div>The study evaluates varying Bi<sub>2</sub>O<sub>3</sub> content's impact on the Bi<sub>2</sub>O<sub>3</sub>-B<sub>2</sub>O<sub>3</sub>-SiO<sub>2</sub>-Na<sub>2</sub>O glass system, where by Bi<sub>2</sub>O<sub>3</sub> addition enhances the density (ρ) and molar volume (V<sub>m</sub>). The elastic moduli decrease due to the increase in V<sub>m</sub>. XRD spectroscopy confirms the amorphous nature. FTIR and Raman spectroscopy indicate shifts in vibrational bands and heightened peak intensities associated with Bi<sub>2</sub>O<sub>3</sub> concentration. It signifies structural alterations owing to Bi-O bond formation and an increase in non-bridging oxygens (NBOs). The radiation shielding properties were investigated from 0.015 MeV to 15 MeV. The linear attenuation coefficient (LAC) at 0.015 MeV varied between 5.851 cm<sup>−1</sup> (for the free Bi<sub>2</sub>O<sub>3</sub> glass) and 210.436 cm<sup>−1</sup> for the glass with 15 mol% Bi<sub>2</sub>O<sub>3</sub>. The LAC showed Bi<sub>2</sub>O<sub>3</sub> incorporation to enhance the glasses' shielding ability. The half value layer (HVL) is affected by the Bi<sub>2</sub>O<sub>3</sub> content, where the HVL at 0.015 MeV reduces from 0.118 to 0.0034 cm due to the addition of 15 mol% Bi<sub>2</sub>O<sub>3.</sub></div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103684"},"PeriodicalIF":2.6,"publicationDate":"2025-05-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144084310","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