Nuclear Engineering and Technology最新文献

Simultaneous measurement of radon exhalation rate and CO2 flux based on accumulation chamber technique with a closed-loop system 基于闭环系统积累室技术的氡呼出率和CO2通量同时测量

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-23 DOI: 10.1016/j.net.2025.103805

Haibo Yi, Chenxi Zu, Jiale Sun, Jiulin Wu, Huiying Li, Zhipeng Liu, Hongbo Xu, Shicheng Luo, Xianfa Mao, Xinyue Yang, Feng Xiao, Hongzhi Yuan, Yanliang Tan

{"title":"Simultaneous measurement of radon exhalation rate and CO2 flux based on accumulation chamber technique with a closed-loop system","authors":"Haibo Yi, Chenxi Zu, Jiale Sun, Jiulin Wu, Huiying Li, Zhipeng Liu, Hongbo Xu, Shicheng Luo, Xianfa Mao, Xinyue Yang, Feng Xiao, Hongzhi Yuan, Yanliang Tan","doi":"10.1016/j.net.2025.103805","DOIUrl":"10.1016/j.net.2025.103805","url":null,"abstract":"<div><div>Carbon dioxide is one of the most important greenhouse gases that contribute to global warming. Radon exhalation rate is an important factor in evaluating environmental radon levels. This paper proposes a method to simultaneously measure the radon exhalation rate and CO<sub>2</sub> flux on the same soil surface based on accumulation chamber technique. Simultaneous measurements of radon exhalation rate (J) and CO<sub>2</sub> flux (F) at the soil surface were made using a portable CO<sub>2</sub> gas analyzer and a RAD7, and the results were obtained by fitting sequences of experimentally measured radon and CO<sub>2</sub> concentrations using mathematical models from existing studies. The experimental results show that radon exhalation rate from the soil surface is significantly and positively correlated with CO<sub>2</sub> flux at the regional scale. The linear fitting results show that J = 7.2 × F, R<sup>2</sup> = 0.86. This simultaneous measurements help to compare and correlate the data and to reveal the potential connection between radon exhalation rate and CO<sub>2</sub> flux.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103805"},"PeriodicalIF":2.6,"publicationDate":"2025-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144687193","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

Impacts of 60Co-γ irradiation on physicochemical characteristics and antioxidant activity of Tibetan medicine Pazhu powder (PP) 60Co-γ辐照对藏药巴珠粉理化特性及抗氧化活性的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-18 DOI: 10.1016/j.net.2025.103584

Yue Yang , Le Zhong , Rang yan po Luo , Zhong si ji Yang , Weishan Qiu , Juhong An , Rui Gu , Shihong Zhong

{"title":"Impacts of 60Co-γ irradiation on physicochemical characteristics and antioxidant activity of Tibetan medicine Pazhu powder (PP)","authors":"Yue Yang , Le Zhong , Rang yan po Luo , Zhong si ji Yang , Weishan Qiu , Juhong An , Rui Gu , Shihong Zhong","doi":"10.1016/j.net.2025.103584","DOIUrl":"10.1016/j.net.2025.103584","url":null,"abstract":"<div><div>In order to explore the effect of <sup>60</sup>Co-γ irradiation on the quality of Tibetan medicine preparations, this study selected Pazhu powder (PP) which has complex and diverse components for research. PP was irradiated at doses of 3, 6, 10, 15, 20, 50, and 100 kGy of <sup>60</sup>Co-γ, Then the effects on color, odor, structural characterization, chemical composition and antioxidant activity were investigated. Results showed that after irradiation, the color, the content of aldehydes and ketones in volatile components were not changed. While the structure and the HPLC fingerprints changed slightly. However, the contents of terpenes, alkanes, amides and alcohols in the volatile components, and all the non-volatile components showed a dose-related decline in irradiated samples. Furthermore, the antioxidant activity increased after irradiation. These findings suggest that <sup>60</sup>Co-γ irradiation has a great influence on the chemical composition of PP. It's necessary to cautiously set reasonable irradiation dose for Tibetan medicine preparations.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103584"},"PeriodicalIF":2.6,"publicationDate":"2025-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656170","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

Development and performance analysis of a PIPS-based detection system for ultra-low Strontium-90 measurement in seawater 基于pips的海水超低锶-90检测系统研制及性能分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-16 DOI: 10.1016/j.net.2025.103797

Younghak Kim, Hyuncheol Kim, Mee Jang, Jaehyeon Seo, Gahyun Kim, Hyemi Cha

{"title":"Development and performance analysis of a PIPS-based detection system for ultra-low Strontium-90 measurement in seawater","authors":"Younghak Kim, Hyuncheol Kim, Mee Jang, Jaehyeon Seo, Gahyun Kim, Hyemi Cha","doi":"10.1016/j.net.2025.103797","DOIUrl":"10.1016/j.net.2025.103797","url":null,"abstract":"<div><div>Strontium-90 (Sr-90) is a key radionuclide for monitoring because of its origin, physicochemical properties, and potential harm to human health. This radionuclide moves with seawater because of its high solubility and is found at trace levels, typically below 1 mBq/kg. Therefore, chemical pretreatment and a highly sensitive detection system are necessary to analyze the concentration of Sr-90 in seawater. In this study, we propose a prototype system based on a passivated implanted planar silicon (PIPS) detector to achieve a minimum detectable activity (MDA) comparable to conventional devices while enhancing user convenience. Finally, both passive and active shielding methods were applied to minimize background radiation contributions. The experimental results showed that the background count rate decreased to approximately one-tenth of its original value, with a count rate of roughly 3.50 cpm for the blank sample. Subsequently, the detection efficiency was optimized by determining the sample shape and detector size, resulting in an estimated value of 51.2 ± 2.7 %. The theoretically calculated MDA was 0.77 mBq/kg for a 1-h measurement and 0.31 mBq/kg for a 6-h measurement, demonstrating the system's applicability for marine radioactivity analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103797"},"PeriodicalIF":2.6,"publicationDate":"2025-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144634525","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 safety of workers for the beta-nuclide removal treatment of the mixed waste from Wolsong nuclear power plant 月松核电站混合废物β -核素去除处理工人的放射安全

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-15 DOI: 10.1016/j.net.2025.103802

Ja Yeong Yoon, Sia Hwang, Hee Reyoung Kim

{"title":"Radiological safety of workers for the beta-nuclide removal treatment of the mixed waste from Wolsong nuclear power plant","authors":"Ja Yeong Yoon, Sia Hwang, Hee Reyoung Kim","doi":"10.1016/j.net.2025.103802","DOIUrl":"10.1016/j.net.2025.103802","url":null,"abstract":"<div><div>This study evaluates the radiological safety of the beta-nuclide removal process for mixed radioactive waste (waste resin, activated carbon, and zeolite) generated during the operation of Wolsong Unit 1. In addition, the potential for reducing worker radiation exposure in accident scenarios was investigated to optimize waste processing capacity. Using the VISIPLAN dose assessment code, external exposure was analyzed in scenarios involving the leakage of airborne radioactive particulates during the beta nuclide removal process. Internal exposure was assessed by taking into account the concentration of airborne radioactive particulates and effectiveness of the protective equipment. The 1 kW beta-nuclide removal reactor processes activated carbon and zeolite, while the 9 kW beta-nuclide removal reactor processes waste resin. Under the conditions of airborne radioactive particulates leakage, the maximum total dose rates for the 1 and 9 kW beta nuclide removal reactors reached 1.51 × 10<sup>−2</sup> and 7.22 × 10<sup>−2</sup> mSv/h, respectively. Based on the annual dose limit of 20 mSv over a five-year period, the permissible operating hours for the 1 kW and 9 kW reactors were determined to be 1325 h and 277 h, respectively. It is expected that these results will contribute to advances in radiation safety assessment techniques for reactor decommissioning and radioactive waste management.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103802"},"PeriodicalIF":2.6,"publicationDate":"2025-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679363","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

Decades of development: A bibliometric analysis of small modular reactor research 几十年的发展：小型模块化反应器研究的文献计量学分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-15 DOI: 10.1016/j.net.2025.103800

Byeong-Je Kim , Young Bae , Philseo Kim

{"title":"Decades of development: A bibliometric analysis of small modular reactor research","authors":"Byeong-Je Kim , Young Bae , Philseo Kim","doi":"10.1016/j.net.2025.103800","DOIUrl":"10.1016/j.net.2025.103800","url":null,"abstract":"<div><div>This study presents a comprehensive bibliometric analysis of global research trends on Small Modular Reactors (SMRs), based on 2080 peer-reviewed publications retrieved from Scopus and Web of Science as of February 2025. Through an analysis of keyword co-occurrence, publication sources, and the contributions of institutions and countries, the study identifies major research areas as well as emerging topics. Safety-related issues, including passive safety systems and natural circulation, remain dominant in the literature, while interest in next-generation reactor types, hybrid energy systems, and integration with renewables continues to grow. In contrast, non-technical dimensions such as public acceptance, policy frameworks, and waste management remain relatively underexplored. A country-level analysis shows that research output is concentrated in a few countries such as the United States, China, South Korea, and Canada, with leading institutions demonstrating topic-specific specialization. Network analysis confirms the centrality of safety-focused research while also identifying limited engagement with socio-political aspects. These findings suggest the need for interdisciplinary research and increased academic attention to issues such as economic feasibility, governance, and long-term waste strategies to support the successful commercialization of SMRs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103800"},"PeriodicalIF":2.6,"publicationDate":"2025-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144686547","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

Development of a BIM-based radiation modeling method and its applicability for nuclear facility decommissioning support 基于bim的核设施退役保障辐射建模方法及其适用性研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-14 DOI: 10.1016/j.net.2025.103801

Hyong Chol Kim, Jae Hee Ro, Moonjoo Gil, Young Jin Lee, Dai Il Kim

{"title":"Development of a BIM-based radiation modeling method and its applicability for nuclear facility decommissioning support","authors":"Hyong Chol Kim, Jae Hee Ro, Moonjoo Gil, Young Jin Lee, Dai Il Kim","doi":"10.1016/j.net.2025.103801","DOIUrl":"10.1016/j.net.2025.103801","url":null,"abstract":"<div><div>A BIM-based radiation modeling method has been developed to estimate radiation source strengths from field-measured dose rates. Using an inverse source strength calculation via the point kernel approach, this method integrates geometric and material information extracted from the BIM model. The developed method has been incorporated into a program tool called BIMRAD, and was validated through various sample cases. The estimation accuracy of this method is considered acceptable, aligning with industry conventions regarding uncertainty tolerance. BIMRAD can generate dose rate distributions and assess radiation work exposures throughout different stages of the dismantling process. Additionally, it provides 3D visualizations to enhance the understanding of radiation fields. This tracking simulation eliminates the need for additional dose rate measurements at each dismantling stage, once the source strengths are determined from initial stage measurements. Furthermore, BIMRAD can be utilized to evaluate alternative approaches for component dismantling and work planning during NPP decommissioning, supporting ALARA analyses by enabling users to retain or remove sources and shielding objects as needed.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103801"},"PeriodicalIF":2.6,"publicationDate":"2025-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144696980","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

Quantitative analysis of impurities in neutron transmutation-doped silicon carbide wafers using neutron activation analysis 用中子活化分析法定量分析中子嬗变掺杂碳化硅晶圆中的杂质

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-12 DOI: 10.1016/j.net.2025.103798

Junhyeok Kim, Byung-Gun Park, Junesic Park, Gi-Doo Kang, Gwang-Min Sun, Myong-Seop Kim

{"title":"Quantitative analysis of impurities in neutron transmutation-doped silicon carbide wafers using neutron activation analysis","authors":"Junhyeok Kim, Byung-Gun Park, Junesic Park, Gi-Doo Kang, Gwang-Min Sun, Myong-Seop Kim","doi":"10.1016/j.net.2025.103798","DOIUrl":"10.1016/j.net.2025.103798","url":null,"abstract":"<div><div>Neutron transmutation doping (NTD) modifies the electrical properties of semiconductor materials by irradiating them with neutrons to introduce dopants with high uniformity. Although NTD has been widely utilized for Si semiconductors, its application to SiC, a wide-bandgap material well suited for high-power devices, has not yet been thoroughly investigated. Conventional doping approaches for SiC face challenges, such as lattice damage and impurity contamination. In this regard, NTD is a promising alternative because of its ability to introduce dopants uniformly. Therefore, this study aims to investigate the characteristics of NTD-SiC wafers irradiated in a HANARO research reactor, focusing on residual radioactivity and impurity mass evaluation via neutron activation analysis. Three radioisotopes (<sup>60</sup>Co, <sup>95</sup>Zr, and <sup>182</sup>Ta) were identified in the NTD-SiC wafers, with <sup>182</sup>Ta exhibiting the highest activity of up to 7330 Bq. Impurity analysis revealed significant contributions from <sup>181</sup>Ta, with its mass reaching up to 1.37 μg. These findings highlight the importance of controlling tantalum impurities to ensure that NTD-SiC meets the safety standards for residual radioactivity, thereby enabling its reliable application in high-power semiconductor devices.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103798"},"PeriodicalIF":2.6,"publicationDate":"2025-07-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144672564","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

Exploration on high-energy and high-dose rate X-ray detection with Bridgman-grown CsPbBr3 single crystal bridgman生长CsPbBr3单晶高能、高剂量率x射线探测的探索

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-12 DOI: 10.1016/j.net.2025.103799

Ahreum Park , Beomjun Park , Jichul Seo , Jangwon Byun , Sung-Jun Park , Sung-Pil Yoon , Juyoung Ko , Jeongho Kim , Wonho Lee , Man-Jong Lee

{"title":"Exploration on high-energy and high-dose rate X-ray detection with Bridgman-grown CsPbBr3 single crystal","authors":"Ahreum Park , Beomjun Park , Jichul Seo , Jangwon Byun , Sung-Jun Park , Sung-Pil Yoon , Juyoung Ko , Jeongho Kim , Wonho Lee , Man-Jong Lee","doi":"10.1016/j.net.2025.103799","DOIUrl":"10.1016/j.net.2025.103799","url":null,"abstract":"<div><div>Perovskite-based semiconductors have emerged as promising candidates for next-generation radiation detectors due to their balanced carrier transport, high effective atomic number, and tunable electronic properties. In this study, we investigate the feasibility of Bridgman-grown CsPbBr<sub>3</sub> (CPB) single crystals for X-ray detection, particularly under high-energy and high-dose-rate conditions. Two types of planar devices, Au/CPB/Au and Ga/CPB/Au, were fabricated and evaluated. The asymmetric Ga/CPB/Au configuration, incorporating a low work function metal, exhibited significantly suppressed dark current and enhanced stability, attributed to Schottky barrier formation. Electrical characterization revealed comparable trap densities between both devices, confirming that performance differences resulted from electrode-induced interface effects rather than fabrication-causing effect such as thermal damage during deposition. The Ga/CPB/Au device demonstrated superior performance across a wide range of X-ray conditions from low dose-rate to diagnostic exposures, with high signal-to-noise ratio (SNR), high sensitivity, and low limit-of-detection (LoD). Notably, the device maintained stable photocurrent and high sensitivity even under harsh X-ray exposures (6 MeV and >1 Gy), validating its robustness and applicability for high energy X-ray dosimeter. This study demonstrates that CPB devices incorporating low work function electrodes are viable candidates for reliable and sensitive X-ray detection across a broad energy and dose range.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103799"},"PeriodicalIF":2.6,"publicationDate":"2025-07-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144661986","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

Probabilistic Model Chain Methodology for evaluating radiological consequences of accidents in High-Temperature Gas-Cooled Reactor 评价高温气冷堆事故辐射后果的概率模型链方法

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-11 DOI: 10.1016/j.net.2025.103779

Piotr Kopka , Michał Spirzewski , Piotr Darnowski

{"title":"Probabilistic Model Chain Methodology for evaluating radiological consequences of accidents in High-Temperature Gas-Cooled Reactor","authors":"Piotr Kopka , Michał Spirzewski , Piotr Darnowski","doi":"10.1016/j.net.2025.103779","DOIUrl":"10.1016/j.net.2025.103779","url":null,"abstract":"<div><div>Dose consequence analysis models are pivotal in Nuclear Safety Analysis, particularly for assessing radiological consequences following nuclear accidents. As many new reactor designs, including High-Temperature Gas-Cooled Reactors (HTGRs), are expected to be located closer to populated areas and propose significantly smaller Emergency Planning Zones (EPZs), accurate consequence analysis becomes increasingly vital. This paper presents a novel Probabilistic Model Chain Methodology (PMCM), beginning with core state estimation using SERPENT2, followed by source term characterization through the Idaho National Laboratory Model, and culminating in the generation of weather scenarios based on empirical models. These data are produced probabilistically, leading to simulations of radionuclide transport and dose assessment using the JRODOS system. The methodology is illustrated using the HTGR TeResa <span><math><mrow><mn>40</mn><mi>M</mi><msub><mrow><mi>W</mi></mrow><mrow><mi>t</mi><mi>h</mi></mrow></msub></mrow></math></span> design and a Depressurized Loss of Forced Cooling accident scenario for the reactor’s location at the National Centre for Nuclear Research in Poland. The resulting dose spatial results are compared with dose limits, as well as dose values across distances from the site, highlighting the highest dose maps. This is achieved through integrated uncertainty across several models, enhancing potential modularity and applicability of the methodology to other reactor types and accident scenarios.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103779"},"PeriodicalIF":2.6,"publicationDate":"2025-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656184","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 of 200 MHz CW He2+ APF-DTLs for 211At production 用于211At生产的200mhz连续波He2+ apf - dtl设计

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-07-10 DOI: 10.1016/j.net.2025.103795

LiangZhou Yao , CanYu Wang , ZhengMao Zhang , Wei Ma , Liping Zou , Zhen Yang , Jinghe Yang , Liang Lu

{"title":"Design of 200 MHz CW He2+ APF-DTLs for 211At production","authors":"LiangZhou Yao , CanYu Wang , ZhengMao Zhang , Wei Ma , Liping Zou , Zhen Yang , Jinghe Yang , Liang Lu","doi":"10.1016/j.net.2025.103795","DOIUrl":"10.1016/j.net.2025.103795","url":null,"abstract":"<div><div>Targeted Alpha-particle Therapy (TAT) has become a significant therapeutic way for cancer, as it can reduce relapsed refractory cancer. <sup>211</sup>At is one of the most promising alpha-emitting radionuclides. To boost its production and facilitate applications, we designed 200 MHz drift tube linacs (DTL) operating in continuous wave (CW) mode, which accelerates a 3 mA He<sup>2+</sup> beam from 6.4 MeV to 28 MeV for <sup>211</sup>At production. Using the alternative phase focusing (APF) beam dynamics to get a compact structure. To ensure high acceleration efficiency, we limit the total cavity length to 2.5 m. The cavity design maintains the gap voltage distribution in close alignment with the beam dynamics, with a maximum deviation of under 1 %. The design achieves 99.98 % beam transmission efficiency. The cavity employs an interdigital H-mode (IH) structure, achieving an unloaded quality factor of 13,635 and a Kilpatrick (Kp) factor of 1.59 in DTL-1, while DTL-2 reaches 14,894 and 1.53 respectively. To ensure stable CW operation, the cooling system has been designed to effectively manage the thermal load during operation, ensuring the system remains within safe limits. This paper presents the detailed design and results of the nuclear medicine linac, including beam dynamics, RF design, and cooling system analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103795"},"PeriodicalIF":2.6,"publicationDate":"2025-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656182","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