Nuclear Analysis最新文献_第4页

Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor PGAA 系统中的温度分布：TRIGA Mark II 反应器中的准直器、快门和过滤器

Nuclear Analysis Pub Date : 2024-07-09 DOI: 10.1016/j.nucana.2024.100120

Jamila Yousfi , Abdessamad Didi , Hamane Lemziouka , Lamiae Mrharrab , Hamid Amsil , Otman Jai , Hamid Bounouira , Khalid Larakil

{"title":"Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor","authors":"Jamila Yousfi , Abdessamad Didi , Hamane Lemziouka , Lamiae Mrharrab , Hamid Amsil , Otman Jai , Hamid Bounouira , Khalid Larakil","doi":"10.1016/j.nucana.2024.100120","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100120","url":null,"abstract":"<div><p>This article examines the impact of temperature on the steel collimator cap and the primary beam shutter. These components will be used to implement the Prompt Gamma Activation Analysis (PGAA) technique in the Moroccan TRIGA Mark-II research reactor. The steel collimator plug is essential for forming the neutron beam, while the main role of the shutter is to stop the beam when the channel is inactive. This study analyzes the effect of temperature on the collimator and shutter system, particularly focusing on the variation in maximum temperature over a month of operation with 8-h cycles per day, the behavior of temperature over 24 h, the total heat flux as a function of the length of the experimental device, the temperature distribution in mild steel (E235) and 304L stainless steel materials, and the total displacement and strain gradient as a function of temperature. All calculations were performed using COMSOL Multiphysics simulation software, based on the finite element method.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 3","pages":"Article 100120"},"PeriodicalIF":0.0,"publicationDate":"2024-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S277318392400020X/pdfft?md5=ed234df0ea998ce112ebc55e0b3b6931&pid=1-s2.0-S277318392400020X-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141607678","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Exploring the impact of anode material on X-ray photon fluence and characteristics: A Monte Carlo simulation study 探索阳极材料对 X 射线光子通量和特性的影响：蒙特卡罗模拟研究

Nuclear Analysis Pub Date : 2024-06-01 DOI: 10.1016/j.nucana.2024.100112

Hassan Ouhadda , Mustapha Zerfaoui , Karim Bahhous , Yassine Oulhouq , Abdessamad Didi , Abdeslem Rrhioua , Dikra Bakari

{"title":"Exploring the impact of anode material on X-ray photon fluence and characteristics: A Monte Carlo simulation study","authors":"Hassan Ouhadda , Mustapha Zerfaoui , Karim Bahhous , Yassine Oulhouq , Abdessamad Didi , Abdeslem Rrhioua , Dikra Bakari","doi":"10.1016/j.nucana.2024.100112","DOIUrl":"10.1016/j.nucana.2024.100112","url":null,"abstract":"<div><p>This study investigates the critical significance of anode material selection in defining the energy spectrum and properties of X-ray photons in medical physics applications. Using the GATE platform and Monte Carlo simulations, a direct relationship between anode material atomic number and photon fluence is demonstrated. As the atomic number increases from Z = 29 (Copper) to Z = 74 (Tungsten), photon fluence rises by 62 %, indicating a substantial impact on X-ray production. Furthermore, the X-ray spectrum is affected by this material-driven changes, revealing a noticeable shift towards higher energy values: the mean energy of the continuous spectrum rises from 46.97 keV for Copper to 49.0 keV for Tungsten. The thermal properties of the material affect the temperature increase at the focal point. Rhodium and Molybdenum have a higher temperature rise than Copper (Cu) and Tungsten (W), because Cu and W have a greater thermal diffusion compared to other materials. These findings underscore the significance of anode material choice in optimizing X-ray systems which may enhance diagnostic accuracy and efficiency in diverse applications.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100112"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000120/pdfft?md5=9a7db82a57fbdb3212adfe5d2e27cfe0&pid=1-s2.0-S2773183924000120-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141139792","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Simulating the impact of electron beam energy deposition on lead target temperature 模拟电子束能量沉积对铅靶温度的影响

Nuclear Analysis Pub Date : 2024-06-01 DOI: 10.1016/j.nucana.2024.100113

Walid Oueslati

{"title":"Simulating the impact of electron beam energy deposition on lead target temperature","authors":"Walid Oueslati","doi":"10.1016/j.nucana.2024.100113","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100113","url":null,"abstract":"<div><p>This study delves into the thermal dynamics induced by an electron beam sourced from the CIRCE III accelerator, focusing on a lead target previously employed at the National Centre for Nuclear Science and Technology (CNSTN) in Tunisia for neutron and photon production. Leveraging FLUKA software, we simulate the intricate interplay between electrons and the target surface, analyzing variations in deposited energy across different target thicknesses. Beyond elucidating the electron-target interaction, our investigation extends to predicting crucial parameters such as the maximum operational threshold and surface temperature distribution of the target. To achieve this, a computational model harnessing the finite volume method is employed, offering insights into the thermal response dynamics and paving the way for optimized operational protocols and target design refinements. Through this comprehensive analysis, we aim to advance the understanding of thermal phenomena in electron-target interactions, thereby bolstering the efficiency and safety of particle accelerator operations in diverse scientific applications.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100113"},"PeriodicalIF":0.0,"publicationDate":"2024-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000132/pdfft?md5=649bffd1aa4b7288312b8b309793fef4&pid=1-s2.0-S2773183924000132-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141324561","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Temperature feedback reactivity analysis for LEU-Fuelled SLOWPOKE-2 research reactor using DRAGON5 and DONJON5 codes 使用 DRAGON5 和 DONJON5 代码对 LEU-Fuelled SLOWPOKE-2 研究反应堆进行温度反馈反应性分析

Nuclear Analysis Pub Date : 2024-04-29 DOI: 10.1016/j.nucana.2024.100111

Otman Jaï , Otmane El Hajjaji , Abdessamad Didi

{"title":"Temperature feedback reactivity analysis for LEU-Fuelled SLOWPOKE-2 research reactor using DRAGON5 and DONJON5 codes","authors":"Otman Jaï , Otmane El Hajjaji , Abdessamad Didi","doi":"10.1016/j.nucana.2024.100111","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100111","url":null,"abstract":"<div><p>The purpose of this study is to provide a new deterministic model for the SLOWPOKE-2 nuclear research reactor at École Polytechnique de Montréal (EPM) with LEU (Low Enriched Uranium) core. Using the latest release of the code system DRAGON5 and DONJON5 and the cross-section data library ENDFB.VII rel.1 evaluation, the developed model is applied to simulate the neutronic behavior of the SLOWPOKE-2 research reactor. We studied the separate temperature effects of the main components of the core (<em>i.e.</em>, fuel, coolant/moderator, beryllium reflector, and water reflector). The contribution of different physical phenomena to the RTC was assessed. The temperature reactivity feedback calculated using the deterministic approach based on the DRAGON5 and DONJON5 code system using the ENDF/B-VII.1 evaluated nuclear data library produced in the WIMD-D4 format is in good agreement. Therefore, this work proves the capability of DRAGON5 and DONJON5 codes, normally used for power reactors, to reliably simulate a low-power research reactor.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100111"},"PeriodicalIF":0.0,"publicationDate":"2024-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000119/pdfft?md5=05c346ab9ad1faff66d878337e3fcf74&pid=1-s2.0-S2773183924000119-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140843260","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Strategic analysis for advancing Morocco's nuclear infrastructure using PESTELE framework 利用 PESTELE 框架推进摩洛哥核基础设施的战略分析

Nuclear Analysis Pub Date : 2024-04-05 DOI: 10.1016/j.nucana.2024.100110

Hafsa Housni , Naila Amrous , Najima Daoudi , Mohamed Jaouad Malzi

{"title":"Strategic analysis for advancing Morocco's nuclear infrastructure using PESTELE framework","authors":"Hafsa Housni , Naila Amrous , Najima Daoudi , Mohamed Jaouad Malzi","doi":"10.1016/j.nucana.2024.100110","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100110","url":null,"abstract":"<div><p>Morocco's exploration of nuclear energy aligns with both climate goals and national energy ambitions, offering a promising low-carbon alternative to conventional fossil fuels. Despite the nation's significant strides in renewable energy, nuclear power remains understudied, revealing a critical literature gap. This research underscores the global imperative to transition to net-zero emissions and the pivotal role nuclear energy plays in addressing climate change. Within the context of Morocco's 2030 plan, which prioritizes renewable energy, nuclear energy stands as an underexplored aspect, lacking comprehensive research. To bridge this gap, the study employs a PESTLE analysis to examine the political, economic, societal, technological, legal, and environmental factors influencing Morocco's nuclear energy landscape. The integration of insights from various sources, including press releases, reports, and scientific publications, ensures a holistic and well-informed perspective on Morocco's nuclear industry. The paper concludes by providing an overview of nuclear energy use on different scales, accompanied by a detailed discussion of the PESTLE analysis outcomes. This approach seeks to contribute valuable insights for informed decision-making and strategic planning in the realm of nuclear energy development.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 2","pages":"Article 100110"},"PeriodicalIF":0.0,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000107/pdfft?md5=e7583478359212119327a9ec9efb8d08&pid=1-s2.0-S2773183924000107-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140549704","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Adsorption of molybdenum (VI) from wastewater using a metal-organic framework material 利用金属有机框架材料吸附废水中的钼 (VI)

Nuclear Analysis Pub Date : 2024-03-01 DOI: 10.1016/j.nucana.2024.100101

Rui Zhang, Wanjun Mu

{"title":"Adsorption of molybdenum (VI) from wastewater using a metal-organic framework material","authors":"Rui Zhang, Wanjun Mu","doi":"10.1016/j.nucana.2024.100101","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100101","url":null,"abstract":"<div><p>With the aim of removing <sup>99</sup>Mo from radioactive wastewater, a metal-organic framework Zr-MOF and its functionalized derivatives (Zr-MOF-SO<sub>4</sub> and Zr-MOF-C<sub>2</sub>O<sub>4</sub>) were prepared as adsorbents, and characterized by SEM, XPS and FI-IR. The results showed the –SO<sub>4</sub> and –C<sub>2</sub>O<sub>4</sub> groups were successfully loaded onto the surface of the original Zr-MOF; the obtained Zr-MOF-SO<sub>4</sub> and Zr-MOF-C<sub>2</sub>O<sub>4</sub> presented different morphologies as small pellets. Both exhibit high adsorption efficiency and fast adsorption rates due to their abundant –SO<sub>4</sub> and –C<sub>2</sub>O<sub>4</sub> surface groups, that provide many adsorption sites for Mo(VI). The maximum adsorption capacities for Mo(VI) of Zr-MOF-SO<sub>4</sub> and Zr-MOF-C<sub>2</sub>O<sub>4</sub> are 192.5 mg g<sup>−1</sup> and 432.3 mg g<sup>−1</sup>, respectively, which is an improvement over other similar adsorbents. In addition, thermodynamic studies indicate a spontaneous exothermic mechanism for the adsorption process. These results demonstrate that anchoring of the functionalized groups is a good way to improve Mo(VI) adsorption capacity of MOF materials.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 1","pages":"Article 100101"},"PeriodicalIF":0.0,"publicationDate":"2024-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000016/pdfft?md5=ccfb26a41c43f064abecba73fcde615c&pid=1-s2.0-S2773183924000016-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140137673","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Determination of 58Fe/54Fe isotope ratios in Chang’E-5 lunar regolith by instrumental neutron activation analysis 利用仪器中子活化分析测定嫦娥五号月球碎屑中的 58Fe/54Fe 同位素比率

Nuclear Analysis Pub Date : 2024-03-01 DOI: 10.1016/j.nucana.2024.100102

Yonggang Yao, Caijin Xiao, Liang Zhao, Yuqing Li, Tianfu Li, Bing Guo, Dongfeng Chen

{"title":"Determination of 58Fe/54Fe isotope ratios in Chang’E-5 lunar regolith by instrumental neutron activation analysis","authors":"Yonggang Yao, Caijin Xiao, Liang Zhao, Yuqing Li, Tianfu Li, Bing Guo, Dongfeng Chen","doi":"10.1016/j.nucana.2024.100102","DOIUrl":"https://doi.org/10.1016/j.nucana.2024.100102","url":null,"abstract":"<div><p>Traditionally, the determination of isotope ratios is analyzed by mass spectrometry (MS) method, which is usually destructive to sample (i.e., sample dissolution). Furthermore, the <sup>58</sup>Fe abundance (0.282%) is generally rather low relative to other Fe isotopes, therefore, <sup>58</sup>Fe/<sup>54</sup>Fe results is not reported in the routine measurement for MS methods. Given the importance of investigating a possible genetic relationship between the stable isotope composition of the Moon and the Earth, here, we firstly report the isotope ratios of <sup>58</sup>Fe/<sup>54</sup>Fe in the Chang’E-5 (CE-5) scooped bulk lunar sample. In this work, the <sup>58</sup>Fe/<sup>54</sup>Fe ratios were analyzed by instrumental neutron activation analysis (INAA) which is essentially distinguished and a potentially complementary advantage for MS in the determination of stable isotope ratios. These data obtained for the CE-5 lunar sample were also compared with those of terrestrial sample GBW07105.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 1","pages":"Article 100102"},"PeriodicalIF":0.0,"publicationDate":"2024-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183924000028/pdfft?md5=2224679dedc13a1664bd7f99e28c6e47&pid=1-s2.0-S2773183924000028-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140042614","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

The blackening of organotin catalyzed silicone adhesive via low dose rate gamma irradiation 通过低剂量率伽马辐照使有机锡催化的硅胶粘合剂变黑

Nuclear Analysis Pub Date : 2023-12-28 DOI: 10.1016/j.nucana.2023.100100

Bo Liu, Lei Yu, Yinyong Ao, Pucheng Wang, Wei Huang

引用次数: 0

Design of emergency solar energy system adjacent the nuclear power plant to prevent nuclear accidents and increase safety 设计核电站附近的应急太阳能系统，以防止核事故并提高安全性

Nuclear Analysis Pub Date : 2023-12-20 DOI: 10.1016/j.nucana.2023.100092

M. Chabook, S. Tashakor

{"title":"Design of emergency solar energy system adjacent the nuclear power plant to prevent nuclear accidents and increase safety","authors":"M. Chabook, S. Tashakor","doi":"10.1016/j.nucana.2023.100092","DOIUrl":"10.1016/j.nucana.2023.100092","url":null,"abstract":"<div><p>Providing sufficient energy in emergency situations in nuclear power plants is of great importance due to their crucial role in improving power plant safety and eliminating disasters.</p><p>Solar power is capable of providing a secure energy source which could be used for emergency power loads. The main goal of this study is application of solar energy for providing emergency loads of the Tehran research reactor. A 100 kW solar power plant connected to the grid and 400 kWh battery pack which is capable of providing 50 kw loads for 8 h is designed. As the first priority, the plant charges the battery pack and discharges excess energy to the power grid. Therefore, the proposed scheme, in addition to increasing safety, also has economic benefits. Design procedure of the power plant was carried out using PVsyst which is international well known software for designing solar power plants and results were investigated. Economic evaluation of the project is carried out using RETSCREEN software and different schemes are evaluated. Due to the critical nature of the power loads and their sensitivity, application of this scheme for providing emergency energy loads of the Tehran research reactor is suggested. Considering the expansion of nuclear safety and the protection of the environment and humanity, we request the respected editors and reviewers of the journal to have positive opinions about the publication of the article.</p></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 1","pages":"Article 100092"},"PeriodicalIF":0.0,"publicationDate":"2023-12-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2773183923000460/pdfft?md5=f88f18ee219edcecf362d1206256f61b&pid=1-s2.0-S2773183923000460-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138987203","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

The lifetime distribution of finite fission chain group around the prompt criticality 迅速临界周围有限裂变链组的寿命分布

Nuclear Analysis Pub Date : 2023-12-04 DOI: 10.1016/j.nucana.2023.100091

Hui Gao, Qilin Xie, Xiaoqiang Fan

引用次数: 0