Nuclear Engineering and Technology最新文献_第4页

Monte Carlo analysis of nitrided Al-6061-T6 as an alternative fuel holder tube in subcritical reactors 氮化Al-6061-T6作为亚临界反应堆替代燃料贮存管的蒙特卡罗分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-27 DOI: 10.1016/j.net.2025.103775

Diego Medina-Castro , Hector Rene Vega-Carrillo , Antonio Baltazar-Raigosa , Tzinnia Gabriela Soto-Bernal , Régulo López-Callejas , Benjamín Gonzalo Rodríguez-Méndez

{"title":"Monte Carlo analysis of nitrided Al-6061-T6 as an alternative fuel holder tube in subcritical reactors","authors":"Diego Medina-Castro , Hector Rene Vega-Carrillo , Antonio Baltazar-Raigosa , Tzinnia Gabriela Soto-Bernal , Régulo López-Callejas , Benjamín Gonzalo Rodríguez-Méndez","doi":"10.1016/j.net.2025.103775","DOIUrl":"10.1016/j.net.2025.103775","url":null,"abstract":"<div><div>The selection of fuel holder tube material in subcritical reactors is critical for operational safety and long-term efficiency. In this study, a Monte Carlo analysis using the MCNP5 code was conducted to evaluate the impact of replacing Al-6061-T6 with its nitrided variant (Al-6061-T6-N), treated via Plasma Immersion Ion Implantation (PIII), as a structural material for the fuel holder tubes in a low-power subcritical reactor. The results showed that the surface modification does not induce significant changes in the effective multiplication factor or in the neutron and gamma-ray spectra. Likewise, the Ambient dose equivalents measured at various positions around the reactor remained virtually unchanged. These findings suggest that the PIII technique preserves the essential nuclear interaction properties of the material without compromising radiological safety. However, complementary experimental studies are recommended to validate its long-term performance under real operating conditions and radiation-induced aging.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103775"},"PeriodicalIF":2.6,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570990","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

Harnessing zirconia and boron synergy: A novel pathway to superior radiation shielding materials 利用氧化锆和硼的协同作用：一种优越的辐射屏蔽材料的新途径

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-26 DOI: 10.1016/j.net.2025.103764

Hanan Akhdar , Ahmed S. Haidyrah , Mohammad W. Marashdeh , K.A. Mahmoud , Islam G. Alhindawy

{"title":"Harnessing zirconia and boron synergy: A novel pathway to superior radiation shielding materials","authors":"Hanan Akhdar , Ahmed S. Haidyrah , Mohammad W. Marashdeh , K.A. Mahmoud , Islam G. Alhindawy","doi":"10.1016/j.net.2025.103764","DOIUrl":"10.1016/j.net.2025.103764","url":null,"abstract":"<div><div>This pioneering work presents a novel approach for manufacturing B-doped ZrO<sub>2</sub>, creating in-situ ZrB<sub>2</sub>O<sub>5</sub> within the ZrO<sub>2</sub> matrix. A cost-effective hydrothermal synthesis using zircon mineral yields a material with exceptional radiation shielding properties. Incorporating B into the ZrO<sub>2</sub> lattice combines ZrO<sub>2</sub>'s gamma attenuation with B's neutron shielding against ionizing radiation. XRD, SEM, and EDX characterization revealed structural properties, phase compositions, and elemental distributions. Monte Carlo simulation and XCOM theoretical modeling investigated B atoms' role in shielding parameters across 0.0332–2.506 MeV γ-ray energies. Results show increased B concentration slightly decreases shielding properties while enhancing mechanical properties including crystallite size, lattice distortions, and dislocation density. B concentration increases from 2.1 to 5.4 wt% decrease LAC values to 65.959–58.613 cm-1 (0.0332 MeV), 0.464–0.461 cm-1 (0.511 MeV), and 0.208–0.270 cm-1 (2.506 MeV). B concentration up to 5.4 wt% enhances mechanical properties without significantly affecting radiation shielding, especially at intermediate energies.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103764"},"PeriodicalIF":2.6,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144518785","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

Framework for evaluating cyber incident response capabilities of nuclear facility operators through operation-based exercises 通过基于操作的演习评估核设施运营商网络事件响应能力的框架

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-26 DOI: 10.1016/j.net.2025.103772

Heewon Aneka Choi , Cheonho Park , JuHyeon Lee , Seungho Jeon , Jung Taek Seo

{"title":"Framework for evaluating cyber incident response capabilities of nuclear facility operators through operation-based exercises","authors":"Heewon Aneka Choi , Cheonho Park , JuHyeon Lee , Seungho Jeon , Jung Taek Seo","doi":"10.1016/j.net.2025.103772","DOIUrl":"10.1016/j.net.2025.103772","url":null,"abstract":"<div><div>Cyberattacks on nuclear facilities can cause unauthorized information leakage and critical impacts on nuclear safety, making an effective cyber incident response system essential. The International Atomic Energy Agency (IAEA) emphasizes the protection of computer-based systems for physical security, nuclear safety, and nuclear material control from cyber threats. Nuclear facility operators must possess the capability to detect and respond to cyber incidents, and this capability can be evaluated through cyber incident response exercises. This study proposes a framework for evaluating nuclear operators' incident response capabilities. The framework analyzes and builds upon IAEA's cyber incident response phases, breaking them down into six phases, defines key activities and evaluation requirements for each phase, and incorporates existing cyber response evaluation technologies. It also presents criteria and performance indicators to evaluate whether these requirements are met. To examine the applicability and practical relevance of the framework, a cyberattack scenario tailored for nuclear facilities is applied to a simulator replicating real-world conditions. The findings of this study provide a systematic and objective way to evaluate response exercises, offering a foundation for effective cyber incident management and minimizing impacts on nuclear facilities.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103772"},"PeriodicalIF":2.6,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144580483","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

Radiological risk and mineralogical analysis of radionuclides in granitic rocks: Environmental insights 花岗岩中放射性核素的放射风险和矿物学分析：环境见解

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-26 DOI: 10.1016/j.net.2025.103759

Sherif A. Taalab , Diaa A. Saadawi , Turki Kh Faraj , Mayeen Uddin Khandaker , Mahmoud R. Khattab , Mohamed Y. Hanfi

{"title":"Radiological risk and mineralogical analysis of radionuclides in granitic rocks: Environmental insights","authors":"Sherif A. Taalab , Diaa A. Saadawi , Turki Kh Faraj , Mayeen Uddin Khandaker , Mahmoud R. Khattab , Mohamed Y. Hanfi","doi":"10.1016/j.net.2025.103759","DOIUrl":"10.1016/j.net.2025.103759","url":null,"abstract":"<div><div>This study investigates the activity concentrations of naturally occurring radionuclides, particularly <sup>238</sup>U, <sup>232</sup>Th, and <sup>40</sup>K, in granitic rocks from the Gabal Abu Garadi region in Central-Eastern Egypt. Using high-purity germanium gamma-ray spectrometry, these radionuclides were quantified and evaluated their spatial distribution and mineralogical associations. The mean concentrations of <sup>232</sup>Th and <sup>238</sup>U were found to be 3944 Bq kg<sup>−1</sup> and 6554 Bq kg<sup>−1</sup>, respectively—significantly exceeding global average values reported by UNSCEAR. Radiological hazard indices, including absorbed dose rate (D<sub>air</sub>), annual effective dose (AED), radium equivalent activity (Ra<sub>eq</sub>), annual gonadal dose equivalent (AGDE), and excess lifetime cancer risk (ELCR) were subsequently calculated to assess the potential health risks posed by these elevated levels. Principal Component Analysis (PCA) and correlation analyses revealed <sup>238</sup>U as the primary contributor to radiological risk in the region. The integration of petrographic and mineralogical studies confirmed the presence of uranium- and thorium-bearing minerals such as uranothorite, thorite, zircon, monazite, and samarskite. The findings highlight the necessity for regulatory oversight and radiation protection measures in areas with similarly enriched geological settings.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103759"},"PeriodicalIF":2.6,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144491748","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

Thiol unit-functionalized ultrastable two-dimensional polymer for adsorption of palladium ions in a nitric acid medium 巯基单元功能化超稳定二维聚合物在硝酸介质中吸附钯离子

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-25 DOI: 10.1016/j.net.2025.103771

Hao Wu , Mai Tanaka , Naoki Osawa , Seong-Yun Kim

{"title":"Thiol unit-functionalized ultrastable two-dimensional polymer for adsorption of palladium ions in a nitric acid medium","authors":"Hao Wu , Mai Tanaka , Naoki Osawa , Seong-Yun Kim","doi":"10.1016/j.net.2025.103771","DOIUrl":"10.1016/j.net.2025.103771","url":null,"abstract":"<div><div>In contrast to the conventional postsynthetic oxidation process for constructing amide linkages, a two-dimensional (2D) polymer (DPA) platform with abundant amide-linkages was directly constructed in this study via a single step using the condensation reaction of trimesyl chloride and melamine. The subsequent postfunctionalization of the as-prepared platform was performed by further reacting it with cysteamine to form thiol units around the DPA platform. Next, the amide-linked thiol unit–functionalized 2D polymer (DPA-BGA) was applied in the selective adsorption of Pd(II) in a nitric acid medium. DPA-BGA exhibited high chemical stability when immersed in 3 M nitric acid for 24 h and high selectivity for Pd(II) over other 13 types of representative metal ions coexisting in the system. Furthermore, using X-ray photoelectron spectroscopy and density functional theory analyses, a plausible adsorption mechanism that involved the interactions between the thiol unit and Pd(II) was identified. Moreover, recycling experiments were performed to demonstrate the reusability of DPA-BGA, which could be used for at least four consecutive adsorption–desorption cycles without a considerable decrease in performance. This study provides a strategy for constructing a stable amide-linked 2D polymer platform and offers a method for its versatile functionalization for application in the field of nuclear research.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103771"},"PeriodicalIF":2.6,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144492133","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 analysis of jet expansion geometry and the influence of pressure waves on the behavior of air discharge processes in subcooled stagnant water 过冷滞水中射流膨胀几何形状及压力波对排气过程影响的实验分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-25 DOI: 10.1016/j.net.2025.103768

D. Blanco , J.L. Muñoz-Cobo , C. Berna

{"title":"Experimental analysis of jet expansion geometry and the influence of pressure waves on the behavior of air discharge processes in subcooled stagnant water","authors":"D. Blanco , J.L. Muñoz-Cobo , C. Berna","doi":"10.1016/j.net.2025.103768","DOIUrl":"10.1016/j.net.2025.103768","url":null,"abstract":"<div><div>Gas jet discharges into liquid media are extensively studied due to their relevance in several industrial processes. They are fundamental in nuclear reactor safety and venting systems, where they play roles in overpressure relief, fission product retention, and aerosol scavenging. The presence of pressure waves in these discharges significantly influences the behavior of the process, determining certain aspects of the jet dynamics. This study focuses on understanding the distribution and propagation of pressure waves within the jet, as they can generate shock waves that alter the geometry, trajectory, and conditions of the jet, introducing additional instabilities and complexities. To conduct this analysis, the JEBEA experimental facility was utilized, performing overexpanded and underexpanded discharges through nozzles with inner diameters ranging from 2 to 6 mm. Direct visualization techniques were employed using a high-speed camera to capture image sequences. Subsequently, image processing methods provided detailed information on the jet dynamics and the influence of pressure waves. Results indicate that shock waves generated near the nozzle significantly impact the intensity and frequency of instabilities in the discharges, varying notably between overexpanded and underexpanded conditions, with frequencies ranging from 5 to 40 Hz in overexpanded jets and 1–11 Hz in underexpanded jets.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103768"},"PeriodicalIF":2.6,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144513603","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

Investigations of density wave oscillation in helical tubes with different configurations sharing the same inlet and outlet headers 具有相同进出口集箱的不同结构螺旋管的密度波振荡研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-24 DOI: 10.1016/j.net.2025.103769

Seunghwan Oh, Jun Ha Hwang, Doh Hyeon Kim, Taeyeon Min, Jeong Ik Lee

{"title":"Investigations of density wave oscillation in helical tubes with different configurations sharing the same inlet and outlet headers","authors":"Seunghwan Oh, Jun Ha Hwang, Doh Hyeon Kim, Taeyeon Min, Jeong Ik Lee","doi":"10.1016/j.net.2025.103769","DOIUrl":"10.1016/j.net.2025.103769","url":null,"abstract":"<div><div>Helical steam generators (HSGs) are crucial in the design of small modular reactors, offering excellent heat transfer performance and compact design characteristics. These features make HSGs viable for both light water and non-light water reactors. However, they pose significant design and operational challenges, particularly with respect to two-phase flow instabilities such as density wave oscillation (DWO). DWO arises from complex thermal-hydraulic interactions within the helical tubes, and failure to clearly define stability boundaries can adversely impact the safety and performance of steam generators and reactor operations. This study provides an in-depth experimental and computational analysis of DWO in HSGs to deepen the understanding of thermal-hydraulic characteristics and DWO mechanisms. The analysis focuses on DWO characteristics observed in two configurations: two identical helical tubes and three helical tubes with differing geometries. An experimental facility utilizing R245fa as the working fluid was designed and constructed to provide detailed insights into two-phase pressure drop and DWO characteristics. The data were further used for the validation and improvement of the MARS-KS code, contributing to the establishment of stability boundaries that can represent complex HSGs. This study aims to serve as foundational data for the design and safety assessment of HSGs in the future.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103769"},"PeriodicalIF":2.6,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144491749","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

Qualification of L-DED 316L for nuclear reactor core applications – Material characteristics before and after neutron irradiation 核反应堆堆芯用L-DED 316L的鉴定。中子辐照前后的材料特性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-24 DOI: 10.1016/j.net.2025.103765

Štěpán Jedlan , Martin Ševeček , Josef Hodek , Michal Brázda , Antonín Prantl , Jaroslav Šoltés , Michael Sovadina , Jitka Klaisnerová , Leoš Křivský

{"title":"Qualification of L-DED 316L for nuclear reactor core applications – Material characteristics before and after neutron irradiation","authors":"Štěpán Jedlan , Martin Ševeček , Josef Hodek , Michal Brázda , Antonín Prantl , Jaroslav Šoltés , Michael Sovadina , Jitka Klaisnerová , Leoš Křivský","doi":"10.1016/j.net.2025.103765","DOIUrl":"10.1016/j.net.2025.103765","url":null,"abstract":"<div><div>The mechanical and microstructural properties of heat treated laser direct energy deposition (L-DED) fabricated austenitic stainless steel 316L were investigated before and after neutron irradiation in the LVR-15 research reactor dry capsule. Tensile tests were carried out at room temperature and elevated temperature followed by light optical microscopy (LOM) and scanning electron microscopy (SEM) analyses of the microstructure. The results showed that the L-DED material exhibited superior ultimate tensile strength (R<sub>m</sub>) and yield strength (Rp<sub>0.2</sub>) mainly due to its smaller grain size (approximately 4x smaller), compared to conventionally manufactured steel. Despite promising mechanical properties, microstructure misorientation analyses revealed incomplete recrystallization after heat treatment, which may affect long-term performance under nuclear reactor conditions. However, no notable differences were observed in the material microstructure between conventionally fabricated and L- DED fabricated materials due to neutron radiation. These findings support the potential of not only laser-deposition but also AM in general as a viable technique for producing in-reactor components.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103765"},"PeriodicalIF":2.6,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144522773","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

Occupational radiation doses to workers handling linkage management equipment for spent nuclear fuel at interim storage facility 在临时贮存设施处理乏燃料连接管理设备工人的职业辐射剂量

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-23 DOI: 10.1016/j.net.2025.103750

Shin-Dong Lee , Dong-Gyu Lee , Geon-Woo Son , Sang-Hwan Lee , Kwang-Pyo Kim

{"title":"Occupational radiation doses to workers handling linkage management equipment for spent nuclear fuel at interim storage facility","authors":"Shin-Dong Lee , Dong-Gyu Lee , Geon-Woo Son , Sang-Hwan Lee , Kwang-Pyo Kim","doi":"10.1016/j.net.2025.103750","DOIUrl":"10.1016/j.net.2025.103750","url":null,"abstract":"<div><div>When managing SNF according to the management stages, if the interchangeability between the transport and storage systems is not considered, inefficient trial-and-error can occur. The metal overpack is a cask that utilizes the DPC to transport and store SNF, and is a linkage management equipment that enhances the interchangeability between management stages. The purpose of this study is to assess a radiation dose for workers handling linkage management equipment in an interim storage facility. For this purpose, radiation exposure scenarios for workers handling linkage management equipment were set. Then, using Monte Carlo computer code, radiation dose rates were calculated for each work location. Finally, total dose and individual dose were calculated for each work. The radiation exposure scenarios for workers were categorized into storage and transportation work. Each work was composed of 16 and 13 tasks. The total radiation dose calculation for the handling linkage management equipment in the interim storage facility for a single DPC showed that storage workers and transportation workers exposed to total 2.144 man-mSv and 1.877 man-mSv, respectively. The results of this study can be used for the development of safety linkage management technologies between the stages of SNF management in the future.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103750"},"PeriodicalIF":2.6,"publicationDate":"2025-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366903","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 characteristic analysis of the pneumatic noise of spring-loaded pressure relief valves 弹簧式减压阀气动噪声数值模拟及特性分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-06-23 DOI: 10.1016/j.net.2025.103760

Dingsheng Xie , Puyu Jiang , Xinyu Zhao , Chunpu Zhang , Maoling Shi , Chaoyong Zong

{"title":"Numerical modeling and characteristic analysis of the pneumatic noise of spring-loaded pressure relief valves","authors":"Dingsheng Xie , Puyu Jiang , Xinyu Zhao , Chunpu Zhang , Maoling Shi , Chaoyong Zong","doi":"10.1016/j.net.2025.103760","DOIUrl":"10.1016/j.net.2025.103760","url":null,"abstract":"<div><div>High-intensity turbulence and interactions among multiple structural parameters are the main factors hindering effective noise prediction in spring-loaded pressure relief valve (SLPRV). On this basis, an in-depth numerical modeling and mechanism analysis are carried out in this paper, where the Computational Fluid Dynamics (CFD) method and Computational Air Acoustic (CAA) are implemented to analysis the noise characteristics of the transient flow field when gas flows through the valve,on this basis, the attenuation characteristics and directivity of the noise were analyzed. In addition, a noise experimental platform for the SLPRV and an acoustic acquisition matrix were set up to verify the accuracy of the simulation results. In order to accurately predict its noise directivity, three key parameters at the valve orifice were selected for research, and a Kriging high-fidelity surrogate model (KHFSM) of the valve structure and noise directivity was constructed. The results show that, under different key structures of the valve, the determination coefficient <em>R</em><sup>2</sup> of the noise predicted by KHFSM reaches 0.969, and the maximum error is less than 1 dB, it can accurately predict the noise directivity of SLPRV, and establish a theoretical and methodological framework underpinning the acoustic optimization of safety valves in nuclear power systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103760"},"PeriodicalIF":2.6,"publicationDate":"2025-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144491747","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