Nuclear Analysis最新文献_第2页

Alpha emitter in samples of antibiotics commonly used in pediatric age groups 儿童年龄组常用抗生素样本中的α发射器

Nuclear Analysis Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100154

Ahmed Abdul Hadi Mohsen , Ali Saeed jassim , Ali Abid Abojassim , Abdulhussein A. Alkufi

{"title":"Alpha emitter in samples of antibiotics commonly used in pediatric age groups","authors":"Ahmed Abdul Hadi Mohsen , Ali Saeed jassim , Ali Abid Abojassim , Abdulhussein A. Alkufi","doi":"10.1016/j.nucana.2025.100154","DOIUrl":"10.1016/j.nucana.2025.100154","url":null,"abstract":"<div><div>This investigation is aimed to assess the level of <sup>222</sup>Rn (radon-222), <sup>226</sup>Ra (radium-226), <sup>238</sup>U (uranium-238), <sup>218</sup>Po (Polonium-218), <sup>214</sup>Po (Polonium-214) in antibiotics that are commonly utilized for pediatrics in Al-Najaf, governorate. Alpha emitters were measured using a CN-85 detector. Additionally, “Annual Average Internal Effective Dose” (AAIED) and “Risk of an Excess Cancer Fatality Per Million Person” (RECFPMP) resulting from <sup>222</sup>Rn, <sup>226</sup>Ra, and <sup>238</sup>U in samples of antibiotics were assessed. The average <sup>222</sup>Rn, <sup>226</sup>Ra, and <sup>238</sup>U values were found to be 2.840, 0.173, and 2.830 Bq/kg, respectively. Moreover, the average AAIED and RECFPMP values which associated with alpha emitters assessment in all medical plant samples were 55.526 nSv/y and 0.214 × 10<sup>−6</sup>, respectively. Finally, the average levels of <sup>218</sup>Po and <sup>214</sup>Po were recorded as 15.926 and 6.716 Bq/m<sup>3</sup>, respectively. After conducting a thorough examination for the resulted data and comparing them with the globally accepted and permissible (<sup>218</sup>Po, <sup>214</sup>Po) limits, it was found that the radiation levels in samples of selected antibiotic medications prescribed for pediatrics were entirely natural and fall within the recommended range. Consequently, there is no cause for concern regarding the radioactive component of these drugs and their safe consumption by children.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100154"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642497","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

Evaluating the level of 226Ra, 232Th and 40K in different building materials 评价不同建筑材料中226Ra、232Th和40K的含量

Nuclear Analysis Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100158

Aqeel A. Elewee , Mohammed S. Alsaffar , Shatha F. Alhous , Murtadha Sh Aswood

{"title":"Evaluating the level of 226Ra, 232Th and 40K in different building materials","authors":"Aqeel A. Elewee , Mohammed S. Alsaffar , Shatha F. Alhous , Murtadha Sh Aswood","doi":"10.1016/j.nucana.2025.100158","DOIUrl":"10.1016/j.nucana.2025.100158","url":null,"abstract":"<div><div>This study evaluates the levels of <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K in various building materials, including brick, cement, sand, gravel, and gypsum, sourced from Al-Shatra in the Dhi-Qar Governorate of Iraq. Measurements were conducted using a NaI (Tl) detector, which is an effective tool for gamma-ray spectrometry. The average activity concentrations measured were 19.70 ± 6.7 Bqkg<sup>−1</sup> for <sup>226</sup>Ra, 20.14 ± 3.3 Bqkg<sup>−1</sup> for <sup>232</sup>Th, and 232.24 ± 91 Bqkg<sup>−1</sup> for <sup>40</sup>K. The calculated mean radium equivalent activity was found to be 66.63 Bqkg<sup>−1</sup>, which is below the internationally accepted threshold of 370 Bqkg<sup>−1</sup>. Both the internal hazard index (Hin) and the external hazard index (Hex) were determined to be less than unity (<1), in accordance with the safe levels recognized by UNSCEAR. Additionally, the average values for the absorbed dose rate (nGyh<sup>−1</sup>), indoor annual effective dose (mSvy<sup>−1</sup>), outdoor annual effective dose (mSvy<sup>−1</sup>), and gamma-ray exposure rate (μRh<sup>−1</sup>) were estimated to be 59.09, 0.29, 0.07, and 138.83, respectively. These parameters are within acceptable limits when compared to the world-permitted values. Therefore, all types of building materials assessed in this study are considered safe and do not pose a significant threat to public health.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100158"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642492","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

Assessment of radiation shielding properties for some concrete mixtures against photon and neutron radiations 某些混凝土混合料对光子和中子辐射屏蔽性能的评价

Nuclear Analysis Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100152

Brahim EL Azzaoui , Ouadie Kabach , Younes EL Abbari , Mohamed Youssef Messous , Khalid Nabaoui , Rabie Outayad , Yassine EL Lkhadiri , El mahjoub ChAKIR , El Mehdi Alibrahmi

{"title":"Assessment of radiation shielding properties for some concrete mixtures against photon and neutron radiations","authors":"Brahim EL Azzaoui , Ouadie Kabach , Younes EL Abbari , Mohamed Youssef Messous , Khalid Nabaoui , Rabie Outayad , Yassine EL Lkhadiri , El mahjoub ChAKIR , El Mehdi Alibrahmi","doi":"10.1016/j.nucana.2025.100152","DOIUrl":"10.1016/j.nucana.2025.100152","url":null,"abstract":"<div><div>This study evaluates fifteen concrete formulations, including standard and hybrid types such as Barite, Iron-Limonite, and Luminite-Colemanite-Barite, to determine their effectiveness in shielding against photon rays and neutrons. Using computational tools like MCNP, Phy-X, and XCOM, key shielding parameters were analyzed, including the Mass Attenuation Coefficient, Half-Value Layer, Mean Free Path, Fast Neutron Removal Cross Section, and Neutron Transmittance. In photon shielding, Iron-Portland concrete demonstrated superior performance, achieving the lowest Half-Value Layer (HVL) of 2.244 cm at 1.33 MeV, which is 42 % better than Ordinary concrete and 57 % better than Barite concrete. Iron-Limonite also showed strong photon attenuation with a Mean Free Path (MFP) of 3.23 cm at 1.33 MeV. For neutron shielding, Iron-Limonite and Ferro-phosphorus concrete recorded the highest Fast Neutron Removal Cross Section (FNRCS) values, reaching up to 0.146 cm⁻<sup>1</sup>, indicating their strong capability to attenuate fast neutrons. Additionally, hybrid concretes like Luminite-Colemanite-Barite provided balanced protection against both photon and neutron radiation. This study highlights the effectiveness of high-density concretes in radiation shielding and underscores the alignment between deterministic and stochastic computational tools used, reinforcing their applicability in enhancing radiation safety.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100152"},"PeriodicalIF":0.0,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143642550","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

Assessment of metal contamination in sediment of Kerala Coast, India using EDXRF technique and Multivariate Statistical method 利用EDXRF技术和多元统计方法评价印度喀拉拉邦海岸沉积物中金属污染

Nuclear Analysis Pub Date : 2024-12-21 DOI: 10.1016/j.nucana.2024.100151

T. Kiruba , P. Jayaprakash , J. Juliet Josephine Joy , J. Venkatamuthukumar , M. Suresh Gandhi , R. Ravisankar

{"title":"Assessment of metal contamination in sediment of Kerala Coast, India using EDXRF technique and Multivariate Statistical method","authors":"T. Kiruba , P. Jayaprakash , J. Juliet Josephine Joy , J. Venkatamuthukumar , M. Suresh Gandhi , R. Ravisankar","doi":"10.1016/j.nucana.2024.100151","DOIUrl":"10.1016/j.nucana.2024.100151","url":null,"abstract":"<div><div>The current study focused on the distribution of heavy metals in sediments from coastline of Kerala, India using Energy Dispersive X-ray Fluorescence (EDXRF) technique. The concentration of V, Cr, Mn, Cu, Zn, Ba, Rb, Zr, As, Br, Sr, and Pb was determined in the sediment samples. The extent of pollution to sediment was assessed via various pollution indices such as enrichment factor (EF), contamination factor (CF), geo accumulation index (I<sub>geo</sub>), metal pollution load index (MPI), degree of contamination (Cd), modified contamination degree (mCd), and potential contamination index (Cp) based on the corresponding background values. The source of origin of heavy metals and the correlation amongst the studied elements was studied using multivariate analysis approach (Pearson correlation matrix, principal component analysis and cluster analysis). The Sediment Quality Guidelines (SQGs) was applied to understand the ecotoxicological significance of heavy metal toxicity. The observed concentration of heavy metals in the studied sediments is due to anthropogenic activity and also from the discharge of municipal wastewater, domestic sewage, fishing harbor activities, industrial and aquaculture pollutants. A regular surveillance and remedial measures for contaminant discharge may reduce the metal content in the study area.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100151"},"PeriodicalIF":0.0,"publicationDate":"2024-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143157907","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 influence of reactor hall on the measurement of reactivity using prompt neutron method 反应炉大厅对瞬发中子法测定反应性的影响

Nuclear Analysis Pub Date : 2024-12-16 DOI: 10.1016/j.nucana.2024.100150

Hui Gao, Meng Li

引用次数: 0

Correlation between microscopic degradation mechanism and macroscopic mechanical property of epoxy resin based on low molecular weight radiolysis products 基于低分子量辐射解产物的环氧树脂微观降解机理与宏观力学性能的关系

Nuclear Analysis Pub Date : 2024-12-01 DOI: 10.1016/j.nucana.2024.100143

Lei Yu , Shuai Chen , Jianming Zhou , Shuai Liu , Bo Liu , Jing Peng , Shuo Hou , Yinyong Ao

{"title":"Correlation between microscopic degradation mechanism and macroscopic mechanical property of epoxy resin based on low molecular weight radiolysis products","authors":"Lei Yu , Shuai Chen , Jianming Zhou , Shuai Liu , Bo Liu , Jing Peng , Shuo Hou , Yinyong Ao","doi":"10.1016/j.nucana.2024.100143","DOIUrl":"10.1016/j.nucana.2024.100143","url":null,"abstract":"<div><div>Low molecular weight radiolysis products play an important role in the performance change and degradation mechanism of polymer materials. In this study, the radiolysis products with low molecular weight of epoxy resin were detected, identified and quantified through solid phase microextraction combined with gas chromatography-mass spectrometry (SPME-GC-MS). The qualitative results showed that most of radiolysis products of epoxy resin were phenols and ketones. The result of principal component analysis showed that the composition of radiolysis products produced at different absorbed doses had obvious difference, indicating that the degradation degree of epoxy resin was different at different absorbed dose. Phenol can be used as an indicator product to reflect the change of tensile strengrh. It indicated that the identification of the radiolysis products was useful for studying the degradation mechanisms and predicting the degradation degree of epoxy resin. Accordingly, the radiation-induced degradation mechanisms were proposed according to the radiolysis products and theoretical calculations.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 4","pages":"Article 100143"},"PeriodicalIF":0.0,"publicationDate":"2024-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143093871","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

New single-toroidal sintered diamond anvil and assembly for high pressure neutron diffraction 用于高压中子衍射的新型单环烧结金刚石砧及组件

Nuclear Analysis Pub Date : 2024-11-08 DOI: 10.1016/j.nucana.2024.100142

Leiming Fang, Gongzhang Yang, Guoliang Niu, Ruiqi He, Jiacheng Sun, Xiping Chen, Lei Xie

{"title":"New single-toroidal sintered diamond anvil and assembly for high pressure neutron diffraction","authors":"Leiming Fang, Gongzhang Yang, Guoliang Niu, Ruiqi He, Jiacheng Sun, Xiping Chen, Lei Xie","doi":"10.1016/j.nucana.2024.100142","DOIUrl":"10.1016/j.nucana.2024.100142","url":null,"abstract":"<div><div><em>In-situ</em> high pressure neutron diffraction experiments, which require a large volume samples, remain challenging, particularly when generating simultaneous high pressure-temperature (<em>P</em>-<em>T</em>) conditions. Although high pressure neutron diffraction experiments have been successfully extended to pressures exceeding 20 GPa, generating pressures over 10 GPa with a large sample volume in the millimeter scale is still difficult. Based on the strategy of introducing gaskets in multi-anvil press, a new single-toroidal sintered diamond anvil and high <em>P</em>-<em>T</em> assembly have been designed for use in the Paris-Edinburgh press, to promoting the neutron diffraction technique with a broadened <em>P</em>-<em>T</em> range. This new single-toroidal set-up can achieve pressure exceeding 14 GPa, with a pressure generating efficiency is nearly same as that of double-toroidal anvil, and exhibits remarkable stability during high <em>P</em>-<em>T</em> experiments. The high <em>P</em>-<em>T</em> neutron diffraction experiments demonstrate that the new set-up can achieves a pressure of 8.7(1) GPa and a temperature of 1380(15) K with a large sample volume of 38 mm<sup>3</sup>.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100142"},"PeriodicalIF":0.0,"publicationDate":"2024-11-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143157908","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

Investigation of photon interaction parameters in Human Body Tissues using GAMOS, FLUKA, and XCOM Studies 利用 GAMOS、FLUKA 和 XCOM 研究调查人体组织中的光子相互作用参数

Nuclear Analysis Pub Date : 2024-10-15 DOI: 10.1016/j.nucana.2024.100141

A. Arectout , H. Boukhal , M. Jarmouni , K. Laazouzi , M. Assalmi , A. Nouayti , M. Hadouachi , H. El Yaakoubi , E. Chakir

{"title":"Investigation of photon interaction parameters in Human Body Tissues using GAMOS, FLUKA, and XCOM Studies","authors":"A. Arectout , H. Boukhal , M. Jarmouni , K. Laazouzi , M. Assalmi , A. Nouayti , M. Hadouachi , H. El Yaakoubi , E. Chakir","doi":"10.1016/j.nucana.2024.100141","DOIUrl":"10.1016/j.nucana.2024.100141","url":null,"abstract":"<div><div>This study aims to evaluate different photon interaction parameters of human body organs at nine photon energies (0.021 keV–1.25 MeV) using GAMOS and FLUKA Monte Carlo codes. The Mass attenuation coefficients, Mean Free Path, Half Value Layer, Tenth Value Layer, and Mass absorption coefficients of the breast, lung, kidney, pancreas, liver, eye lens, thyroid, brain, ovary, heart, large intestine blood, skin, spleen, muscle, and cortical bone were investigated and compared against the standard values available from the tables of XCOM database. This comparison demonstrated a good agreement, with all calculated values deviating less than 6 %. In addition, the values obtained with the GAMOS code were similar to those obtained using the FLUKA code. These comparisons indicate very good agreement and revealed that both FLUKA and GAMOS codes can be used as a computational tool for determining the photon interaction parameters of any material and also different energies, whose data are not available in the literature.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100141"},"PeriodicalIF":0.0,"publicationDate":"2024-10-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142527819","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

Optimizing neutron shielding: A specialised container approach for Disused Sealed Radioactive Sources and orphan neutron emitters 优化中子屏蔽：废弃密封放射源和无主中子发射器的专用容器方法

Nuclear Analysis Pub Date : 2024-10-10 DOI: 10.1016/j.nucana.2024.100140

Brahim EL Azzaoui , Ouadie Kabach , Mohamed Youssef Messous , El mahjoub Chakir , El Mehdi Alibrahmi

{"title":"Optimizing neutron shielding: A specialised container approach for Disused Sealed Radioactive Sources and orphan neutron emitters","authors":"Brahim EL Azzaoui , Ouadie Kabach , Mohamed Youssef Messous , El mahjoub Chakir , El Mehdi Alibrahmi","doi":"10.1016/j.nucana.2024.100140","DOIUrl":"10.1016/j.nucana.2024.100140","url":null,"abstract":"<div><div>Shielding Disused Sealed Radioactive Sources (DSRSs) and orphan neutron sources, such as <sup>252</sup>Cf, pose challenges due to the high penetration of neutrons, induced radioactivity in shielding materials, and the limited availability of compact, effective shielding materials. This study addresses these challenges by proposing a specialized container for the safe transport, conditioning, and disposal of neutron-emitting DSRSs and orphan sources. The computational tool that was used in this study is the Monte Carlo N-Particle (MCNP). The investigation begins with an examination of moderation materials, including high-density polyethylene (HDPE), paraffin, and water-extended polyester (WEP). Subsequently, four concrete types, namely Ordinary, Barite, Portland, and Serpentine Concrete, are scrutinized. Employing a comprehensive methodology, the design of the container is optimized to effectively moderate and absorb neutron emissions. The findings of this study demonstrate that the designed compact container can safely handle activities exceeding those studied, effectively managing up to 10 μg (about 0.2 GBq) <sup>252</sup>Cf without exceeding 25 μSv/h at the outer container contact. This suggests a promising solution for the secure management of high-activity neutron-emitting sources.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 1","pages":"Article 100140"},"PeriodicalIF":0.0,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142441061","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

A comparative analysis of the NaI detector response function using GAMOS and FLUKA Monte Carlo simulations 利用 GAMOS 和 FLUKA 蒙特卡罗模拟对碘化钠探测器响应函数进行比较分析

Nuclear Analysis Pub Date : 2024-09-23 DOI: 10.1016/j.nucana.2024.100138

A. Arectout , H. Boukhal , E. Chakir , M. Jarmouni , M. Assalmi , T. El Ghalbzouri , O.E. Belhaj , Mohamed Drissi El-Bouzaidi , A. Nouayti , I. Zidouh , H. El Yaakoubi

{"title":"A comparative analysis of the NaI detector response function using GAMOS and FLUKA Monte Carlo simulations","authors":"A. Arectout , H. Boukhal , E. Chakir , M. Jarmouni , M. Assalmi , T. El Ghalbzouri , O.E. Belhaj , Mohamed Drissi El-Bouzaidi , A. Nouayti , I. Zidouh , H. El Yaakoubi","doi":"10.1016/j.nucana.2024.100138","DOIUrl":"10.1016/j.nucana.2024.100138","url":null,"abstract":"<div><div>This work aims to study the response function of a 2″×2″ NaI(Tl) scintillation detector using Monte Carlo simulations. A precise mathematical model of the NaI(Tl) scintillator was developed using both FLUKA and GAMOS Monte Carlo simulation software. The photon pulse height distributions of the NaI(Tl) without influence of its energy resolution, obtained with FLUKA and GAMOS codes, were converted into a real NaI(Tl) response function using the necessary conversion process. Spectral characteristics such as full-energy peak efficiency, energy resolution, peak-to-Compton ratio, and peak-to-total ratio were investigated by simulation at different gamma-ray energy obtained from <sup>109</sup>Cd, <sup>137</sup>Cs, <sup>54</sup>Mn, <sup>65</sup>Zn, and <sup>60</sup>Co sources. The simulated spectra from the GAMOS code were consistent with those generated by the FLUKA code. Additionally, the comparison between simulated results and experimental data demonstrated good agreement. The validation of the computational models used for the NaI(Tl) detector in both FLUKA and GAMOS software was successfully achieved, confirming the accuracy of the simulations in replicating the detector's response.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"3 4","pages":"Article 100138"},"PeriodicalIF":0.0,"publicationDate":"2024-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323148","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