Nuclear Engineering and Technology最新文献_第2页

Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor fcm燃料微气冷堆多物理场耦合分析方法的建立

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-16 DOI: 10.1016/j.net.2025.103645

Kuaiyuan Feng , Qufei Song , Yihu Wang , Hui Guo , Tenglong Cong , Yao Xiao , Hanyang Gu

{"title":"Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor","authors":"Kuaiyuan Feng , Qufei Song , Yihu Wang , Hui Guo , Tenglong Cong , Yao Xiao , Hanyang Gu","doi":"10.1016/j.net.2025.103645","DOIUrl":"10.1016/j.net.2025.103645","url":null,"abstract":"<div><div>At present, Fully Ceramic Microencapsulated (FCM) fuel with randomly dispersed tri-structural isotropic (TRISO) particles is widely used in gas-cooled microreactors. Gas-cooled microreactors usually exhibit limited volume and complex structure, with tightly coupled multi-physical fields inside the core, presenting challenges for multiphysics analysis. In this work, a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor within the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is developed and verified. The fuel assembly calculation results show that the generated multi-group cross-section (MGXS) at different temperature points exhibits high computational accuracy. The MOC-MOOSE results exhibit a high computational accuracy in <em>k</em><sub><em>eff</em></sub>, power distribution, and temperature field. Meanwhile, the calculation cost for the MOC-MOOSE method is only 10 % of that required by the benchmark solver, demonstrating high computational efficiency. At last, the full-core multiphysics coupling was conducted. The three-dimensional pin-by-pin fuel power distribution was obtained, with the highest power occurring in the outermost fuel rods of the peripheral fuel assemblies at the middle plane of the axial active region. The maximum fuel, matrix, and coolant temperatures are 1698 K, 1206 K, and 1002 K, separately.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103645"},"PeriodicalIF":2.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868812","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

Stringent environmental policies: How they shape the future of nuclear energy generation 严格的环境政策：它们如何塑造核能发电的未来

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-15 DOI: 10.1016/j.net.2025.103650

Chuan Zhang , Mian Gohar Rahman Zafar , Francis Gaudreault , Ousama Ben-Salha , Adeeb Alhebri

{"title":"Stringent environmental policies: How they shape the future of nuclear energy generation","authors":"Chuan Zhang , Mian Gohar Rahman Zafar , Francis Gaudreault , Ousama Ben-Salha , Adeeb Alhebri","doi":"10.1016/j.net.2025.103650","DOIUrl":"10.1016/j.net.2025.103650","url":null,"abstract":"<div><div>Nuclear energy is a low-carbon energy source that can replace fossil fuels in the energy mix. However, the serious risks associated with nuclear energy generation must be effectively managed. Environmental policy stringency can counter these risks by compelling the polluted firms and industries to switch to clean energy sources, thereby enhancing the production of alternative and clean energy sources, including nuclear energy. Empirical evidence in this context is missing, confirming a gap in the nuclear energy literature. In order to plug this gap, this research examines how stringent environmental policies can enhance nuclear energy generation in the leading 18 nuclear energy-producing nations from 1995 to 2021. In order to examine the empirical connection between environmental policy and nuclear energy generation, we employ the CS-ARDL model. The results indicate that stringent environmental policies lead to a decline in long-term nuclear energy generation. Nonetheless, the environmental policy does not affect short-term nuclear energy generation. Moreover, environmental technology, financial advancement, and sustainable development significantly enhance long-term nuclear energy generation. In the short term, all these variables do not substantially affect nuclear energy generation except environmental technology, which improves nuclear energy generation. Given the significance of environmental policy stringency for nuclear energy production, we suggest that the government needs to implement strict environmental policies with a special focus on the energy sector.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103650"},"PeriodicalIF":2.6,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868810","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

Comparative analysis of VVER-1200 core inventory considering non-uniform and uniform reactor core power distribution 考虑非均匀和均匀堆芯功率分布的VVER-1200堆芯库存对比分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-14 DOI: 10.1016/j.net.2025.103635

Md Rosaidul Mawla , Anisur Rahman , Md. Shafiqul Islam

{"title":"Comparative analysis of VVER-1200 core inventory considering non-uniform and uniform reactor core power distribution","authors":"Md Rosaidul Mawla , Anisur Rahman , Md. Shafiqul Islam","doi":"10.1016/j.net.2025.103635","DOIUrl":"10.1016/j.net.2025.103635","url":null,"abstract":"<div><div>The impact of reactor core power distribution on radionuclide inventory calculations in the VVER-1200 reactor was analyzed using the ORIGEN, focusing on 135 radionuclides categorized into seven groups. The study considers two core models: one utilizing the dual enrichment strategy (4.4 % and 4.9 %, averaging 4.68 %) and another with a uniform enrichment of 4.79 %. Under non-uniform power distribution, activation product activity is calculated as 2.252 × 10<sup>18</sup> Bq for the mixed enrichment (4.4 % & 4.9 %) and 2.229 × 10<sup>18</sup> Bq for the uniform 4.79 % enrichment. Under uniform power distribution, these values are 2.364 × 10<sup>18</sup> Bq and 2.193 × 10<sup>18</sup> Bq, respectively. Similarly, actinides and their daughters exhibit total activities of 8.279 × 10<sup>19</sup> Bq and 8.190 × 10<sup>19</sup> Bq under non-uniform power, compared to 8.662 × 10<sup>19</sup> Bq and 8.003 × 10<sup>19</sup> Bq under uniform power. Fission products dominate the radionuclide inventory, with total activities of 3.895 × 10<sup>20</sup> Bq and 3.893 × 10<sup>20</sup> Bq in non-uniform scenarios, versus 3.830 × 10<sup>20</sup> Bq and 3.826 × 10<sup>20</sup> Bq in uniform scenarios. Although the overall radionuclide inventory difference between uniform and non-uniform distributions is minimal, localized regions in non-uniform distributions exhibit higher activity due to high burnup. These findings are crucial for accident analysis, safety assessment, radioactive waste management, and the decommissioning of nuclear facilities.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103635"},"PeriodicalIF":2.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143825907","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

Design and validation of shielding for a neutron generator using MCNP6 基于MCNP6的中子发生器屏蔽设计与验证

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-14 DOI: 10.1016/j.net.2025.103634

Jae Chang Kim, Junehyung Lee Bernaski, Sehwan Seol, Ju Hyung Kim, Yong Kyun Kim

{"title":"Design and validation of shielding for a neutron generator using MCNP6","authors":"Jae Chang Kim, Junehyung Lee Bernaski, Sehwan Seol, Ju Hyung Kim, Yong Kyun Kim","doi":"10.1016/j.net.2025.103634","DOIUrl":"10.1016/j.net.2025.103634","url":null,"abstract":"<div><div>This study presents the design, fabrication, and experimental validation of a shielding facility for the DD-108 neutron generator installed for active neutron interrogation applications such as differential die-away analysis. The shielding structure was optimized using MCNP6 simulations to meet regulatory dose limits of 20 mSv/y for radiation workers and 1 mSv/y for the general public. The regulatory dose limits were achieved by utilizing the existing concrete and lead structures and designing additional high density polyethylene shielding based on neutron and photon dose assessments. Various effective dose conversion coefficients were considered to ensure a conservative evaluation. The facility was constructed, and calibrated dosimeter measurements confirmed that neutron and photon doses were up to 50 % and 76 % lower than simulation predictions. These results reflect the conservative assumptions applied in the modeling, ensuring robust safety margins. The shielding facility met all licensing requirements, leading to the first regulatory approval of a DD-108 neutron generator in South Korea. This validation demonstrates the practicality of MCNP6-based shielding design and provides valuable insights for future neutron generator shielding applications.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103634"},"PeriodicalIF":2.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828643","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

Simulation study of a high-efficiency diamond thermal neutron 3D detector with double-conversion layer 双转换层高效金刚石热中子三维探测器的仿真研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-14 DOI: 10.1016/j.net.2025.103649

Hongyun Wang , Xiaochuan Xia , Jian Cui , Shuqi Meng , Wenyi Shao , Yang Liu , Yuhao Xie , Shulu Xie , Deyu Wang , Wei Jiang , Ruirui Fan , Hongwei Liang

{"title":"Simulation study of a high-efficiency diamond thermal neutron 3D detector with double-conversion layer","authors":"Hongyun Wang , Xiaochuan Xia , Jian Cui , Shuqi Meng , Wenyi Shao , Yang Liu , Yuhao Xie , Shulu Xie , Deyu Wang , Wei Jiang , Ruirui Fan , Hongwei Liang","doi":"10.1016/j.net.2025.103649","DOIUrl":"10.1016/j.net.2025.103649","url":null,"abstract":"<div><div>Diamond is commonly employed as a semiconductor material for thermal neutron detectors due to its excellent properties such as high-temperature resistance and superior irradiation hardness. In this paper, the diamond thermal neutron detectors (DTND) were simulated using the Geant4 Monte Carlo simulation toolkit. The different types and numbers of conversion layers and the structure of the DTND were optimized by comparing the simulation results of the deposit energy spectra and the detection efficiency. DTND with a double-conversion-layer planar structure, using both <sup>6</sup>LiF and <sup>10</sup>B, can boost detection efficiency from 4.4 % to 7.2 %, overcoming the limitations of the reaction probabilities of a single-conversion layer (<sup>6</sup>LiF or <sup>10</sup>B). Furthermore, for the 3D structure, the relationship between the trench spacing, the trench width, and the detection efficiency was established by integrating extensive simulation data from single- and double-conversion-layer trench-type detectors. Ultimately more than 70 % detection efficiency was obtained on a structure with a dual-sided, double-conversion layer at a trench depth of 100 μm. Our work provides valuable instructions for practical engineering applications of DTND.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103649"},"PeriodicalIF":2.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143847320","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

Validation of BAM:EuMn thermographic phosphor for high-temperature surface thermometry on thermoelectric generator heat sink BAM: eun热成像荧光粉用于热电发电机散热器高温表面测温的验证

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-12 DOI: 10.1016/j.net.2025.103647

Seongmin Kang , Kyungjun Lee , Myeongjin Seo , Hideo Mori , Jae-Ho Jeong

{"title":"Validation of BAM:EuMn thermographic phosphor for high-temperature surface thermometry on thermoelectric generator heat sink","authors":"Seongmin Kang , Kyungjun Lee , Myeongjin Seo , Hideo Mori , Jae-Ho Jeong","doi":"10.1016/j.net.2025.103647","DOIUrl":"10.1016/j.net.2025.103647","url":null,"abstract":"<div><div>This study demonstrates phosphor thermometry as a high-temperature surface measurement technique for evaluating the heat exchange performance of Thermoelectric Generators (TEGs). We designed a wind tunnel chamber to assess the heat exchange performance of TEG heat sink fins. Surface temperature measurements in the 200–300 °C range were successfully performed under forced convection on both flat plate specimens and heat sink using BAM:EuMn phosphor with an intensity-mode technique. Comparative analysis between thermocouple measurements in both natural and forced convection conditions using flat plate specimens revealed an average error of 1.84 °C, indicating high measurement accuracy with a relative error of less than 1 %. CFD analysis was conducted under identical conditions to verify the experimental setup's feasibility. The high-temperature surface temperature measurement technique developed in this study offers advantages for observing temperature evolution characteristics over extended periods using relatively inexpensive cameras and lighting equipment. The technique also effectively captures temperature evolution under instantaneous transient heat transfer conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103647"},"PeriodicalIF":2.6,"publicationDate":"2025-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842461","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

Effect of non-uniform distribution of radioactivity in human body on measurements using HPGe detector based scanning bed whole body counter 人体放射性不均匀分布对基于HPGe探测器的扫描床全身计数器测量的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-12 DOI: 10.1016/j.net.2025.103636

I.S. Singh , Rajesh Sankhla , M.Y. Nadar , Lokpati Mishra , P. Prathibha , S. Anilkumar , P.D. Sawant , Probal Chaudhury

{"title":"Effect of non-uniform distribution of radioactivity in human body on measurements using HPGe detector based scanning bed whole body counter","authors":"I.S. Singh , Rajesh Sankhla , M.Y. Nadar , Lokpati Mishra , P. Prathibha , S. Anilkumar , P.D. Sawant , Probal Chaudhury","doi":"10.1016/j.net.2025.103636","DOIUrl":"10.1016/j.net.2025.103636","url":null,"abstract":"<div><div>In-vivo monitoring of radiation workers for high energy photon emitters is carried out using whole body counters. These are calibrated using standard radioactive sources uniformly distributed in BOMAB phantom. In the case of inhalation intake of Type S compounds, radioactivity is retained in lungs for a long time resulting in non-uniform distribution. In this paper, the effect of non-uniform distribution of activity in human body is studied on the direct measurement using shadow shield bed whole body counter (SSBWBC) with BOMAB and LLNL phantoms. First, the system was calibrated with known amount of <sup>133</sup>Ba, <sup>137</sup>Cs, <sup>60</sup>Co and <sup>40</sup>K uniformly distributed in water filled BOMAB phantom. Then, the system was calibrated with known amount of <sup>152</sup>Eu and <sup>241</sup>Am uniformly distributed in the lungs of LLNL phantom. The multiple gamma energies of radionuclides were used to determine the counting efficiencies for uniformly distributed activity in whole body as well as in the lungs. The study shows when uniform distribution of radionuclides in the whole body is assumed but activity is confined in the lungs only, measured activity is overestimated by 15 to 20 %. This results in similar overestimation in intake and CED.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103636"},"PeriodicalIF":2.6,"publicationDate":"2025-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143822384","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

SphiNx: A SN-DFEM neutron transport code based on the MOOSE framework SphiNx：一个基于MOOSE框架的SN-DFEM中子输运代码

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-09 DOI: 10.1016/j.net.2025.103641

Hu Zhang , Da Li , Tianliang Hu , Guangchun Zhang , Duoyu Jiang , Qianwei Chen , Henglin Hu

引用次数: 0

Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion FeCrAlMo-xZr燃料包层合金热腐蚀过程的显微组织与力学演化

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-09 DOI: 10.1016/j.net.2025.103637

Chundong Wang , Xijie Wu , Jie Pan , Huawei Zhang , Jun Li , Jiwei Lin , Ping Cao , Cheng Su , Cong Li , Meiyi Yao , Xueshan Xiao

{"title":"Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion","authors":"Chundong Wang , Xijie Wu , Jie Pan , Huawei Zhang , Jun Li , Jiwei Lin , Ping Cao , Cheng Su , Cong Li , Meiyi Yao , Xueshan Xiao","doi":"10.1016/j.net.2025.103637","DOIUrl":"10.1016/j.net.2025.103637","url":null,"abstract":"<div><div>The microstructural and mechanical evolution of the Fe-13Cr-6Al-2Mo-<em>x</em>Zr (<em>x</em> = 0.15, 0.5, 1.0 wt%) alloys for fuel cladding throughout various hot corrosion processes, such as thermal aging at 475 °C in air and high temperature oxidation at 1200 °C under an atmosphere of Ar + water vapour, were investigated. The findings indicate that as the Zr content increases, the grain size of the alloys becomes progressively smaller. During thermal aging, the secondary Laves phase precipitated within the grains and Mo segregation occurred on the grain boundaries, ultimately forming the μ phase. The plasticity decreased by degrees with aging time due to the formation and growth of precipitates, while the tensile strength increased only during the early aging period and then remained almost unchanged. The steam oxidation rate was promoted with the Zr content because of the smaller grain size and the deeper internal oxidation resulting from the faster diffusion of oxygen in ZrO<sub>2</sub> than that in Al<sub>2</sub>O<sub>3</sub>.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103637"},"PeriodicalIF":2.6,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828646","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

Organ dose estimation for Occupationally Exposed Workers in medical practice in Gabon during the period 2013–2023 2013-2023年期间加蓬医疗实践中职业暴露工人器官剂量估计

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-04-08 DOI: 10.1016/j.net.2025.103630

Philippe Ondo Meye , Guy-Blanchard Dallou , Beaud Conrad Mabika Ndjembidouma , Charles Chaley , Sylvère Yannick Loemba Moandza , Patrice Ele Abiama , Saidou Saidou , Germain Hubert Ben-Bolie

{"title":"Organ dose estimation for Occupationally Exposed Workers in medical practice in Gabon during the period 2013–2023","authors":"Philippe Ondo Meye , Guy-Blanchard Dallou , Beaud Conrad Mabika Ndjembidouma , Charles Chaley , Sylvère Yannick Loemba Moandza , Patrice Ele Abiama , Saidou Saidou , Germain Hubert Ben-Bolie","doi":"10.1016/j.net.2025.103630","DOIUrl":"10.1016/j.net.2025.103630","url":null,"abstract":"<div><div>This paper aimed to update the results of a previous study in terms of H<sub>p</sub> (10) for the period 2013–2023 and to estimate organ doses based on H<sub>p</sub> (10) and exposure conditions (radiation energy and irradiation geometry) of Gabonese Occupationally Exposed Workers (OEWs) in the medical practice. A total of 1181 dose records for 243 OEWs were evaluated. Doses were collected for an eleven-year period, from 2013 to 2023. Fourteen public and private hospitals were involved. Organ absorbed doses were estimated using measured H<sub>p</sub> (10) values and two dose conversion coefficients: (1) the air kerma-to-H<sub>p</sub> (10) conversion coefficient and (2) the air kerma-to-organ dose conversion coefficient. H<sub>p</sub> (10) and organ dose values were assigned a 95 % expanded uncertainty confidence interval based on a previously established function. The mean ± standard deviation and the range of years of exposure of OEWs were 4.9 ± 2.7 years and (1–10) years, respectively. The mean and median annual doses values determined in the present study were close to those determined in a previous study. The overall mean cumulative dose for this period was 1.6 mSv (1.2–2.3) mSv. Organs with the highest mean cumulative absorbed doses were skin, 2.0 mGy (1.5–2.8) mGy, eye-lens, 1.9 mGy (1.5–2.7) mGy, testes, 1.7 mGy (1.3–2.5) mGy, thyroid, 1.5 mGy (1.2–2.2) mGy, and female breast, 0.9 mGy (0.7–1.2) mGy. Finally, the study showed that cumulative organ doses estimated in the present study are significantly lower than those presented in the literature.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103630"},"PeriodicalIF":2.6,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842460","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