Nuclear Engineering and Technology最新文献_第9页

Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site Wolsung 核电厂 CANDU 乏燃料贮存罐的寿命热分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-18 DOI: 10.1016/j.net.2024.07.041

Tae Gang Lee , Taehyung Na , Byongjo Yun , Jae Jun Jeong

{"title":"Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site","authors":"Tae Gang Lee , Taehyung Na , Byongjo Yun , Jae Jun Jeong","doi":"10.1016/j.net.2024.07.041","DOIUrl":"10.1016/j.net.2024.07.041","url":null,"abstract":"<div><div>CANDU spent fuels in the Wolsung site have been stored in dry storage systems, such as concrete canisters and modular air-cooled storage system. The primary role of the canister is to ensure the integrity of the fuel during the storage period, which is significantly influenced by temperature. Thus, thermal analysis for the canister's components, especially for fuel cladding, is essential to demonstrate its safety. The thermal analysis has been conducted mainly for predicting the peak cladding temperature (PCT) since high temperature of the fuel can promote oxidation and cracking. As the expiration of storage license approaches, fuel transfer to final disposal should be prepared. This also requires a thermal analysis to predict minimum cladding temperature (MCT), which is related with brittleness. So, it is crucial to accurately predict both PCT and MCT during entire storage period. The cladding temperature is primarily influenced by decay heat and ambient conditions. The lifetime PCT may occur during summer at the beginning of storage, while the lifetime MCT occurs during winter at the end of storage. In this study, we calculated the PCT and MCT during the entire storage period using a realistic thermal analysis model and, subsequently, conducted their uncertainty analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5320-5329"},"PeriodicalIF":2.6,"publicationDate":"2024-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141771273","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX 提高蒙特卡罗代码 NECP-MCX 中多组散射矩阵计算的理算效率和精度

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-17 DOI: 10.1016/j.net.2024.07.038

Hongchun Wu, Shuai Qin, Yunzhao Li, Jinkang Shi, Qingming He, Liangzhi Cao

{"title":"Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX","authors":"Hongchun Wu, Shuai Qin, Yunzhao Li, Jinkang Shi, Qingming He, Liangzhi Cao","doi":"10.1016/j.net.2024.07.038","DOIUrl":"10.1016/j.net.2024.07.038","url":null,"abstract":"<div><div>Two issues arise in the calculation of the multi-group scattering matrix when employing a continuous-energy Monte Carlo code for generating homogenized multi-group cross-sections. Firstly, the analog estimator is used to evaluate group-to-group elements, which leads to large statistical uncertainty. Secondly, employing the scalar flux as the weighting function in generating the high-order scattering matrix introduces errors in fast reactor calculations. For the first issue, the repeated collision approach and pre-tabulated cross-section approach are adopted to improve the tally efficiency. For the second issue, the average scattering cosine is calculated based on the conservation of the mean square displacement of neutrons, which is then used to correct the first-order self-scattering cross-section. To evaluate the effectiveness of the above approaches, a PWR pin-cell problem and fast reactor core problems are tested. The results demonstrate that: 1) The figure of merit for multi-group scattering matrix calculations was improved by 8–12 times with the pre-tabulated cross-section approach. 2) Biases of <em>k</em><sub>eff</sub> were reduced from over 500 pcm to less than 300 pcm when using the corrected self-scattering cross-section. 3) The corrected self-scattering cross-section also yielded higher accuracy for the assembly power calculations, where the maximum biases are reduced from 5 % to 1 %.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5305-5312"},"PeriodicalIF":2.6,"publicationDate":"2024-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141786273","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis 蒙特卡洛反应堆分析中用于内联临界棒位置搜索计算的中子平衡法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-16 DOI: 10.1016/j.net.2024.07.037

YuGwon Jo, Jaewoon Yoo, Jae-Yong Lim

引用次数: 0

Assessment of environmental hazard impacts in building materials (Marble), Gabal El-Galala El-Bahariya, Northeastern Desert, Egypt 建筑材料（大理石）对环境危害影响的评估，埃及东北部沙漠，Gabal El-Galala El-Bahariya

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-16 DOI: 10.1016/j.net.2024.07.005

M.Y. Hanfi , R.M. Abd El Rahman , Mohammad S. Alqahtani

{"title":"Assessment of environmental hazard impacts in building materials (Marble), Gabal El-Galala El-Bahariya, Northeastern Desert, Egypt","authors":"M.Y. Hanfi , R.M. Abd El Rahman , Mohammad S. Alqahtani","doi":"10.1016/j.net.2024.07.005","DOIUrl":"10.1016/j.net.2024.07.005","url":null,"abstract":"<div><div>Galala limestone is widely used for construction and ornamental purposes and is known throughout the world under many commercial names, including Galala White, Galala Golden, Galala Creama and Galala Classic. Using a HPGe spectrometer, about 20 samples from the marble building industry were radiometrically analyzed and the gamma radiation emitted by the radionuclides <sup>238</sup>U, <sup>232</sup>Th and <sup>40</sup>K was evaluated. The measurements performed showed that the concentrations of these radionuclides were 15 ± 13, 6 ± 4 and 1100 ± 330 Bq kg<sup>−1</sup>, respectively. It's important to note that all these recorded values do not exceed the internationally reported average levels of 33, 45 and 412 Bq kg<sup>−1</sup>for each individual element. The annual effective dose (AED) was estimated. The mean value of AED, 0.07 mSv/y, is comparable to the permissible average of 0.07 mSv/y, respectively. The relationship between radionuclides and their radiological hazard characteristics was studied using various multivariate statistical techniques such as Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). The results indicate that the main contributors to the radiological hazard associated with marble are uranium and potassium. As a result, the use of marble in building materials may not pose a significant risk to public health.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 4966-4974"},"PeriodicalIF":2.6,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141848132","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure 研究外压下螺旋蒸汽发生器管的几何形状和材料特性对塌陷压力的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.033

Gyo-Geun Youn , Kwanghyun Ahn , Myeong-Woo Lee

{"title":"Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure","authors":"Gyo-Geun Youn , Kwanghyun Ahn , Myeong-Woo Lee","doi":"10.1016/j.net.2024.07.033","DOIUrl":"10.1016/j.net.2024.07.033","url":null,"abstract":"<div><div>In this paper, a numerical study was conducted to analyze the effect of the geometry (tube thickness, ovality, and helical diameter) and material properties of once through steam generator tubes subjected to external pressure on collapse pressure. The outer diameter of the steam generator tube was fixed at 17 mm, and the tube thickness was changed to 2.5 mm, 2.29 mm, and 1.27 mm. Ovality was considered for three cases of 0 %, 4 %, and 8 %, and three cases for helical diameter were considered: 577 mm, 937 mm, and 1297 mm. As material properties, elastic perfectly plastic property that ignores plastic hardening and real material property that reflect plastic hardening were considered. At the helical diameter (<em>D</em><sub><em>m</em></sub>/<em>d</em><sub><em>o</em></sub> ≥ 34) considered in this paper, the effect of collapse pressure due to helical bending did not appear on ovalities and both material properties. On the other hand, the wall thickness affected the collapse pressures according to the material properties when ovality occurred (>0 %). This is explained because the collapse mechanism varies depending on the thickness.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5257-5268"},"PeriodicalIF":2.6,"publicationDate":"2024-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141702098","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

“Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography” "利用断层扫描技术对质子束相空间进行二维分布重构和幅射诊断"

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.036

Jeong-Jeung Dang , Seunghyun Lee , Han-sung Kim , Hyeok-jung Kwon

{"title":"“Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography”","authors":"Jeong-Jeung Dang , Seunghyun Lee , Han-sung Kim , Hyeok-jung Kwon","doi":"10.1016/j.net.2024.07.036","DOIUrl":"10.1016/j.net.2024.07.036","url":null,"abstract":"<div><div>A two-dimensional distribution of a proton beam in phase space was reconstructed using beam profile data and a tomography technique in this study. These beam profile data were acquired by a wire scanner under various beam optics conditions, employing an experimental procedure identical, in principle, to the quadrupole magnet (QM) scan method to diagnose beam parameters. According to beam optics, beam profile data measured while changing the QM current is the same as that measured while rotating the beam distribution in the phase space. Thus, the set of the beam profile data can be converted into a sinogram, serving as source data for tomography. A filtered-back-projection (FBP) method is applied to reconstruct the beam distribution from this sinogram. However, if the range and distribution of the rotation angle are not sufficient, the reconstructed distribution data will be inaccurate, which will negatively affect beam parameter evaluation. To solve this limitation, a simulator incorporating the beam optics theory with the tomography was developed to derive an efficient experimental condition. The beam distribution in the phase space was successfully reconstructed, and the beam parameters evaluated from this were also confirmed to match well with the values obtained from the QM scan.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5291-5296"},"PeriodicalIF":2.6,"publicationDate":"2024-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141694180","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A review of COHRISK: Multihazard risk quantification software for nuclear power plants COHRISK：核电厂多重危害风险量化软件综述

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.035

Eujeong Choi , Shinyoung Kwag , Jung-Han Kim , Jeong-Gon Ha , Daegi Hahm , Minkyu Kim

{"title":"A review of COHRISK: Multihazard risk quantification software for nuclear power plants","authors":"Eujeong Choi , Shinyoung Kwag , Jung-Han Kim , Jeong-Gon Ha , Daegi Hahm , Minkyu Kim","doi":"10.1016/j.net.2024.07.035","DOIUrl":"10.1016/j.net.2024.07.035","url":null,"abstract":"<div><div>A combination of more than one natural hazard can occur simultaneously by their inherent correlation or by coincidence. One well-known multihazard incident, the Tohoku earthquake-tsunami in Japan 2011, led to a core damage accident at the Fukushima Daiichi nuclear power plant (NPP) and caused significant damage to its community. But despite this accident raising significant awareness of multihazard safety in the nuclear safety engineering community, multihazard risk quantification methods and tools for NPPs are relatively less investigated when compared to those for single hazards. At the same time, some multihazard tools developed outside the nuclear engineering industry are inadequate for extension to NPPs because of the complex NPP systems and the response correlation between the systems, structures, and components. To resolve this problem, the authors have been conducting a series of projects on developing a method for multihazard risk quantification of NPP systems and have launched the related quantification software, Combined Hazard RISK (COHRISK). This paper presents a review of COHRISK including its conceptual background, methodology development, architecture, and future work.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5281-5290"},"PeriodicalIF":2.6,"publicationDate":"2024-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141691292","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Mesh morphing-based pre-processing and numerical simulation of blockage accident in lead–bismuth fast reactor fuel assembly 基于网格变形的铅铋快堆燃料组件堵塞事故预处理与数值模拟

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.032

Hao Sun, Yong Ouyang, Zihua Liu, Huo Liang, Hanyan Luo, Zhikang Lin

引用次数: 0

Feasibility of a position-sensitive Cherenkov radiation detector using a reflector-coated liquid light guide 使用反射器涂层液体光导的位置敏感切伦科夫辐射探测器的可行性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.030

Sangjun Lee, Siwon Song, Jae Hyung Park, Seunghyeon Kim, Hyungi Byun, Jinhong Kim, Seokhyeon Jegal, Bongsoo Lee

{"title":"Feasibility of a position-sensitive Cherenkov radiation detector using a reflector-coated liquid light guide","authors":"Sangjun Lee, Siwon Song, Jae Hyung Park, Seunghyeon Kim, Hyungi Byun, Jinhong Kim, Seokhyeon Jegal, Bongsoo Lee","doi":"10.1016/j.net.2024.07.030","DOIUrl":"10.1016/j.net.2024.07.030","url":null,"abstract":"<div><div>In this study, a Cherenkov radiation sensor was developed utilizing a reflector-coated liquid light guide (LLG). In the proposed configuration, a reflector replaced one of the two photomultiplier tubes (PMTs), forming the core sensing element alongside the LLG, with gamma-ray (<sup>60</sup>Co and <sup>137</sup>Cs) and a beta-ray (<sup>90</sup>Sr) emitters employed to assess its performance as a position-sensitive detector. The time-of-flight method was utilized to determine time differences corresponding to source positions. Position spectra were generated based on these time differences, with the Cherenkov radiation count rates compared across different types of reflectors to identify the optimal choice. We compared position spectra obtained from two PMTs and one PMT with a reflector, confirming the ability to detect multiple sources. Subsequently, each source was positioned perpendicular or parallel to the sensor axis to capture position spectra. The results demonstrate the sensor's potential as a long-distance position-sensitive detector. By leveraging the simplicity of a single PMT system, the proposed sensor facilitates challenging tasks such as pipeline inspection or non-destructive testing of radioactive waste drums.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5231-5238"},"PeriodicalIF":2.6,"publicationDate":"2024-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141711928","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition 高浓度蒸汽产生条件下铈射流破裂的三维 cfd 模拟

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.034

Jeong-Hyun Eom, Ji-Won Choi, Gi-Young Tak, In-Sik Ra, Huu Tiep Nguyen, Hae-Yong Jeong

{"title":"A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition","authors":"Jeong-Hyun Eom, Ji-Won Choi, Gi-Young Tak, In-Sik Ra, Huu Tiep Nguyen, Hae-Yong Jeong","doi":"10.1016/j.net.2024.07.034","DOIUrl":"10.1016/j.net.2024.07.034","url":null,"abstract":"<div><div>The complexity of ex-vessel phenomena during a severe accident limits the most previous CFD applications only to hydrodynamic aspects. The present study performs numerical analysis of jet breakup and debris bed formation under intensive steam generation using the STAR-CCM + code. The CFD prediction of the MATE06 experiment demonstrates jet breakup progression patterns consistent to the experiment results. The predicted jet breakup lengths are in good agreement with the MATE 06 data in earlier stage. However, some disparities of the leading-edge position between the MATE 06 and the simulation are predicted in late stage. This is attributed to non-periodic repetitions of the detachment and reattachment of some fragmented segments to the jet column. The difference of frictional force or shear stress between the experiment and CFD simulation also causes uncertainty in the amount of steam generation. In overall, the present study becomes significant to simulate successfully the series of jet breakup process and debris bed formation under intensive steam generation condition. In future studies, it is required to upgrade the current model through more evaluation of experiments and to develop much sophisticated models which provide an enhanced realistic simulation of ex-vessel phenomena.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5269-5280"},"PeriodicalIF":2.6,"publicationDate":"2024-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141688788","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0