Fusion Engineering and Design最新文献

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Protium enrichment by polymer electrolyte fuel cell with hydrogen gas circulation 聚合物电解质燃料电池氢气循环富集Protium
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-20 DOI: 10.1016/j.fusengdes.2025.115399
Toranosuke Nago, Mikito Ueda, Hisayoshi Matsushima
{"title":"Protium enrichment by polymer electrolyte fuel cell with hydrogen gas circulation","authors":"Toranosuke Nago,&nbsp;Mikito Ueda,&nbsp;Hisayoshi Matsushima","doi":"10.1016/j.fusengdes.2025.115399","DOIUrl":"10.1016/j.fusengdes.2025.115399","url":null,"abstract":"<div><div>Hydrogen isotope separation is an important technology in various fields, including medicine, materials science, and nuclear energy. In this study, deuterium separation was performed using a polymer electrolyte fuel cell (PEFC) equipped with a gas circulation system. A hydrogen gas tank was integrated into the gas circulation line, enabling separation over a larger gas volume and achieving substantial H enrichment. The H concentration (<em>C</em><sub>H</sub>) in the hydrogen gas was monitored during the experiment using a mass spectrometer. During power generation, H was enriched in the hydrogen gas, and <em>C</em><sub>H</sub> increased from 24.2 at % to 54.6 at %. To evaluate the relationship between gas consumption and the H enrichment, the separation factor (<em>αₜ</em>) was considered. The value of <em>α<sub>t</sub></em> was higher than that of mass balance calculation. The present study suggested the separation was improved by the vapor phase chemical exchange reaction.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115399"},"PeriodicalIF":2.0,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144866331","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
Preliminary results on the removal of retained hydrogen by ECR discharge cleaning in Helimak 赫利马克ECR放电清洗法去除残留氢的初步结果
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-20 DOI: 10.1016/j.fusengdes.2025.115397
Shuqi Yang , Yaowei Yu , Xiang Zhu , Muquan Wu , Hang Li , Gongshun Li , Fei Wen , Xiaodong Lin , Xiang Gao
{"title":"Preliminary results on the removal of retained hydrogen by ECR discharge cleaning in Helimak","authors":"Shuqi Yang ,&nbsp;Yaowei Yu ,&nbsp;Xiang Zhu ,&nbsp;Muquan Wu ,&nbsp;Hang Li ,&nbsp;Gongshun Li ,&nbsp;Fei Wen ,&nbsp;Xiaodong Lin ,&nbsp;Xiang Gao","doi":"10.1016/j.fusengdes.2025.115397","DOIUrl":"10.1016/j.fusengdes.2025.115397","url":null,"abstract":"<div><div>The Helimak is a compact toroidal steady-state device that has been reassembled and upgraded at Shenzhen University to serve as a dedicated platform for wall-conditioning studies. In this work, electron cyclotron resonance (ECR) plasma cleaning driven by 2.45 GHz radio frequency (RF) waves is systematically investigated. The effects of the toroidal magnetic field (TF), RF power, and wall temperature on hydrogen removal are quantified. Lowering TF from 0.098 T to 0.048 T shifts the ECR resonance layer closer to the inner wall, significantly enhancing cleaning efficiency. Increasing RF power from 3 to 8 kW raises the plasma density and further improves removal performance. Elevating the wall temperature to 90°C provides an additional boost; at 8 kW, the removal rate at 90°C is approximately 5.5 times higher than that at room temperature. These findings highlight the importance of resonance positioning and elevated wall temperature for effective hydrogen decontamination, and they support the feasibility of Electron Cyclotron Wall Conditioning (ECWC) techniques in future fusion devices.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115397"},"PeriodicalIF":2.0,"publicationDate":"2025-08-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144879533","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 development status of the ITER Radial Gamma Ray Spectrometer ITER射线伽马能谱仪的设计与研制现状
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-16 DOI: 10.1016/j.fusengdes.2025.115376
Federico Scioscioli , Giulia Marcer , Alessandro Ciurlino , Stefano Colombi , Bruno Coriton , Andrea Dal Molin , Jan Dankowski , Giuseppe Gorini , Andrei Kovalev , Andrea Muraro , Massimo Nocente , Marica Rebai , Davide Rigamonti , Marco Tardocchi , Gabriele Croci
{"title":"Design and development status of the ITER Radial Gamma Ray Spectrometer","authors":"Federico Scioscioli ,&nbsp;Giulia Marcer ,&nbsp;Alessandro Ciurlino ,&nbsp;Stefano Colombi ,&nbsp;Bruno Coriton ,&nbsp;Andrea Dal Molin ,&nbsp;Jan Dankowski ,&nbsp;Giuseppe Gorini ,&nbsp;Andrei Kovalev ,&nbsp;Andrea Muraro ,&nbsp;Massimo Nocente ,&nbsp;Marica Rebai ,&nbsp;Davide Rigamonti ,&nbsp;Marco Tardocchi ,&nbsp;Gabriele Croci","doi":"10.1016/j.fusengdes.2025.115376","DOIUrl":"10.1016/j.fusengdes.2025.115376","url":null,"abstract":"<div><div>The ITER Radial Gamma Ray Spectrometer (RGRS) is an ITER diagnostic located in the Equatorial Port 01 undergoing its Preliminary Design Review and foreseen for Phase DT1 (2041). RGRS is expected to measure the density profile and energy distribution of <span><math><mi>α</mi></math></span>-particles through reactions with <sup>10</sup>B, the current and maximum energy of runaway electrons through bremsstrahlung emissions, and fusion power via a radiative channel of the DT reaction. The diagnostic employs LaBr<sub>3</sub> scintillators coupled with PMTs along 4 radial lines of sight, with LiH attenuators to reduce the background due to direct neutrons and a heavily hydrogenated and borated concrete-like mixture for neutron shielding.</div><div>Performance assessments indicate RGRS can fulfil its functions regarding runaway electrons, while the feasibility of measuring <span><math><mi>α</mi></math></span>-particles is uncertain due to the intense gamma-ray background observed at JET. Further study is needed to confirm this measurement possibility. Additionally, while fusion power measurements appear possible, satisfying ITER requirements necessitates detailed knowledge of the gamma-ray-to-neutron branching-ratio of the DT reaction, which will be investigated through dedicated experiments, and possibly gamma-ray attenuators to reduce background.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115376"},"PeriodicalIF":2.0,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144852545","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
As-built based method for virtual alignment and assembly of the ITER tokamak 基于已建的ITER托卡马克虚拟对准与装配方法
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-15 DOI: 10.1016/j.fusengdes.2025.115392
Francesca Giovanna Lanzotti , Edoardo Pompa , Gianluca Picci , Alessandro Lo Bue , Giuseppe Di Gironimo , Domenico Marzullo , Gabriele D’Amico
{"title":"As-built based method for virtual alignment and assembly of the ITER tokamak","authors":"Francesca Giovanna Lanzotti ,&nbsp;Edoardo Pompa ,&nbsp;Gianluca Picci ,&nbsp;Alessandro Lo Bue ,&nbsp;Giuseppe Di Gironimo ,&nbsp;Domenico Marzullo ,&nbsp;Gabriele D’Amico","doi":"10.1016/j.fusengdes.2025.115392","DOIUrl":"10.1016/j.fusengdes.2025.115392","url":null,"abstract":"<div><div>In the project development of large fusion machines, the alignment and assembly phases represent an open challenge. Each mechanical component that constitutes the whole machine assembly and fixtures is affected by an intrinsic geometrical variation due to manufacturing and assembly processes. The complexity of the assembly together with the unavoidable geometrical imperfection can affect the expected machine functionalities. In this context, Reverse Engineering activities, aiming at obtaining the as-built of the components, coupled with virtual fitting studies, defining optimum alignment using the real shape of the components, become powerful risk mitigation tools in the assembly phases. This work presents a systematic method, complementary to the methodology currently followed in the ITER project, for the as-built management and for the validation of alignment phases of such a complex assembly. The first phase is to identify the key assembly requirements which drive the alignment of the ITER assembly. Then, the database for the requirement collection is clearly organized following the proper nomenclature rules and its architecture for data collection and analysis is indeed set up. Four virtual fitting pilot studies are presented to show how the methodology is helpful to assess the assembly requirements in a defined alignment scenario.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115392"},"PeriodicalIF":2.0,"publicationDate":"2025-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144841234","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
Low cycle fatigue life prediction for neutron-irradiated and nonirradiated RAFM steels via machine learning 基于机器学习的中子辐照和非辐照RAFM钢低周疲劳寿命预测
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-14 DOI: 10.1016/j.fusengdes.2025.115394
Hussein Zahran , Aleksandr Zinovev , Dmitry Terentyev , Ali Aouf , Magd Abdel Wahab
{"title":"Low cycle fatigue life prediction for neutron-irradiated and nonirradiated RAFM steels via machine learning","authors":"Hussein Zahran ,&nbsp;Aleksandr Zinovev ,&nbsp;Dmitry Terentyev ,&nbsp;Ali Aouf ,&nbsp;Magd Abdel Wahab","doi":"10.1016/j.fusengdes.2025.115394","DOIUrl":"10.1016/j.fusengdes.2025.115394","url":null,"abstract":"<div><div>EUROFER97 and other Reduced Activation Ferritic-Martensitic (RAFM) steels are candidate structural materials for fusion reactors. Qualification of these steels requires the assessment of their performance under fatigue loading especially after exposure to neutron irradiation. However, the significantly high costs and engineering complexity of performing such tests make the experiments on irradiated material difficult. Therefore, alternative methods to predict the fatigue life of RAFM steels are deemed beneficial. In this study, machine learning was used to predict the fatigue life of irradiated and non-irradiated RAFM steels utilizing published experimental data. Four algorithms were benchmarked: Random Forest Regression (RF), Support Vector Regressor (SVR), Gradient Boosted Regressor (GBR), and MultiLayer Perceptron (MLP). Predictions were made based on two scenarios: one scenario with yield strength as input along with the fatigue test condition, and the second scenario without the yield strength. The results showed that RF and GBR were the best performing algorithms, with <em>R</em><sup>2</sup> score between 0.9522 and 0.9696 on the training set and between 0.9058 and 0.9249 on the validation set. The Mean Absolute Percentage Error (MAPE) score was between 0.3 and 0.43 % on the training set and 0.7 and 1.2 % on the validation set. The quality of prediction of fatigue life without using the yield strength was shown to be almost equal to that in the first scenario. SHAP analysis revealed that strain range was the most influential input feature, while GBR showed greater sensitivity to secondary features such as temperature and diameter. GBR also captured more nuanced interactions between input variables, particularly in irradiated datasets, confirming its superior ability to model complex fatigue behaviour. The ability of these algorithms to predict the fatigue life corresponding to test conditions not used for training was checked using 15 % of the collected database as a prediction set, which included fatigue life of irradiated materials. Results indicated that these algorithms were able to predict the fatigue life of this set with 83-87 % of the points lying within the factor of two from the experimental value.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115394"},"PeriodicalIF":2.0,"publicationDate":"2025-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828606","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
Thermo-mechanical analysis of a steering mirror with dielectric bulk for the ECRH system of DTT DTT ECRH系统介质体转向镜的热力学分析
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-13 DOI: 10.1016/j.fusengdes.2025.115389
Alfredo Pagliaro , Francesco Braghin , Alessandro Bruschi , Daniele Busi , Eliana De Marchi , Francesco Fanale , Gustavo Granucci , Afra Romano , Fabio Zanon
{"title":"Thermo-mechanical analysis of a steering mirror with dielectric bulk for the ECRH system of DTT","authors":"Alfredo Pagliaro ,&nbsp;Francesco Braghin ,&nbsp;Alessandro Bruschi ,&nbsp;Daniele Busi ,&nbsp;Eliana De Marchi ,&nbsp;Francesco Fanale ,&nbsp;Gustavo Granucci ,&nbsp;Afra Romano ,&nbsp;Fabio Zanon","doi":"10.1016/j.fusengdes.2025.115389","DOIUrl":"10.1016/j.fusengdes.2025.115389","url":null,"abstract":"<div><div>The steerable launcher mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system of the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat loads acting on the mirrors, internal water-cooling channels are necessary to control temperature and deformation. A variable-depth complementary spiral cooling channel was considered in this study. A dielectric material with high thermal conductivity was selected as a potential candidate to reduce eddy currents, this mitigating magnetic torques and mechanical stress, while guaranteeing adequate cooling. Thermo-structural simulations (FSI) were conducted to assess the mirror's resistance to induced stresses, its deformations, and cooling performance. A transient analysis showed that thermal steady-state is the worst-case thermal loading condition during the entire experiment. Additionally, the thermo-structural behavior of various materials was analyzed to demonstrate the superior performance of the selected dielectric material. The cooling channel was subsequently adapted to a prototype mirror, on which CFD and FSI simulations were performed to validate the numerical model against future real-world experiments. Finally, crack propagation analysis confirmed the feasibility of using technical ceramics for the launching mirror, paving the way for dielectric materials in the ECRH system of DTT.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115389"},"PeriodicalIF":2.0,"publicationDate":"2025-08-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828601","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
Flow-induced fretting in DEMO divertor targets equipped with swirl tapes: Numerical investigation through one-way fluid-structure interaction simulations 装有旋流带的DEMO导流器靶流致微动:单向流固耦合模拟的数值研究
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-13 DOI: 10.1016/j.fusengdes.2025.115307
S. Baydoun , A. Durif , G. Ricciardi , N. Sashidharan , S. Fouvry , P. Arnaud , V.A. Yastrebov , C. Harrington , M. Diez , T. Hirai , M. Richou , J․H You
{"title":"Flow-induced fretting in DEMO divertor targets equipped with swirl tapes: Numerical investigation through one-way fluid-structure interaction simulations","authors":"S. Baydoun ,&nbsp;A. Durif ,&nbsp;G. Ricciardi ,&nbsp;N. Sashidharan ,&nbsp;S. Fouvry ,&nbsp;P. Arnaud ,&nbsp;V.A. Yastrebov ,&nbsp;C. Harrington ,&nbsp;M. Diez ,&nbsp;T. Hirai ,&nbsp;M. Richou ,&nbsp;J․H You","doi":"10.1016/j.fusengdes.2025.115307","DOIUrl":"10.1016/j.fusengdes.2025.115307","url":null,"abstract":"<div><div>The divertor targets in DEMO, sustaining a quasi-steady state heat flux up to 20 MW/m², are made of pure tungsten armoring actively water-cooled CuCrZr pipes. The heat exhaust capability of the divertor targets can be improved by adding a swirl tape in the cooling channel. Analysis from WEST samples and several laboratory studies highlight that under DEMO-like cooling conditions, the insertion of swirl tapes in the pipes triggers surface wear damage. This is due to flow-induced vibrations of the swirl tape within the hosting pipe leading to fretting which takes place whenever two bodies in contact, submitted to normal load, undergo micro-displacement oscillatory motion. Fretting wear damage is a serious problem that may reduce the lifetime of the divertor components and their thermal efficiency. Hence, the objective of this study is to quantify tribological loadings in the divertor inducing fretting through fluid-structure interaction simulations (FSI) to set up dedicated fretting tests in laboratory. One-way FSI simulations are performed using URANS (Unsteady Reynolds-Averaged Navier-Stokes equations) and LES (Large Eddy Simulation) to assess the fluid pressure in order to perform transient structural analysis allowing the estimation of stresses, deformations and tribological loadings (contact forces and sliding amplitude) at the CuCrZr pipe/swirl-tape contact area. Benefits and drawbacks of each modelling method (LES and URANS) are discussed. The numerical outputs highlight that one-way FSI simulation reflects complex contact loading between the swirl and the pipe involving fretting sliding with both impact and fluctuating normal forces. The obtained loads drive the choice of the normal forces and the sliding distance ranges which will be explored in laboratory via fretting wear experiments.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115307"},"PeriodicalIF":2.0,"publicationDate":"2025-08-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828603","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
Conceptual study of DTT ICRH antenna designs optimizing remote handling strategy DTT ICRH天线设计优化远程处理策略的概念研究
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-13 DOI: 10.1016/j.fusengdes.2025.115378
G. Camera , A. Cioffi , S. Ceccuzzi , F. Marino , F.G. Lanzotti , G. Di Gironimo
{"title":"Conceptual study of DTT ICRH antenna designs optimizing remote handling strategy","authors":"G. Camera ,&nbsp;A. Cioffi ,&nbsp;S. Ceccuzzi ,&nbsp;F. Marino ,&nbsp;F.G. Lanzotti ,&nbsp;G. Di Gironimo","doi":"10.1016/j.fusengdes.2025.115378","DOIUrl":"10.1016/j.fusengdes.2025.115378","url":null,"abstract":"<div><div>The Ion Cyclotron Resonance Heating (ICRH) antenna for the Divertor Tokamak Test (DTT) facility is expected to be not only cantilevered, radially movable and fully cooled, but also remote handled: the additional challenge of the Remote Handling (RH) from the inner of the chamber has been posed. The remote assembly and disassembly will be performed through the HYper Redundant MANipulator (HYRMAN) and clearly require the design of the linking interfaces between the remote handled parts and the components placed behind. But the development of in-vessel Radio Frequency (RF) contacts proved in the past to be very challenging, raising concerns on their long-term reliability. Therefore, the toroidal size of the current straps has been reduced to make them, and the relative RF contacts, directly pass through the Vacuum Vessel equatorial port. Thus, only the leftover geometry of the ICRH antenna frontal part should be remote handled and alternative RH strategies have been analyzed and compared. The selecting criteria have been based on the requirements to be fulfilled like the payload limit of the HYRMAN and the RF performance, and on the subcomponents functions to be guaranteed like the side straps shielding. Furthermore, the choice process has also considered technical reasons such as the number of RH operations and interfaces to robotic arms, the minimum number of cooling circuits and the flexion risk. In compliance with the chosen criteria, the most satisfying solution has been selected to be considered for the design of the gripper to be attached to the HYRMAN.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115378"},"PeriodicalIF":2.0,"publicationDate":"2025-08-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828602","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
Preliminary structural design of WCCB TBM-set WCCB tbm机组结构初步设计
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-13 DOI: 10.1016/j.fusengdes.2025.115393
Wenhai Guan , Takanori Hirose , Yoshinori Kawamura , Hiroyasu Tanigawa
{"title":"Preliminary structural design of WCCB TBM-set","authors":"Wenhai Guan ,&nbsp;Takanori Hirose ,&nbsp;Yoshinori Kawamura ,&nbsp;Hiroyasu Tanigawa","doi":"10.1016/j.fusengdes.2025.115393","DOIUrl":"10.1016/j.fusengdes.2025.115393","url":null,"abstract":"<div><div>This study presents a preliminary structural design of the water-cooled ceramic breeder (WCCB) Test Blanket Module (TBM)-set, proposed by the Institutes for Quantum Science and Technology in Japan, which is intended for installation in ITER's equatorial port No. 18. The research investigates the local tritium breeding ratio (TBR), the temperature distribution of the submodule, and the structural integrity assessment of the WCCB TBM-set under the ITER load environment to complete the review of the preliminary design activities. Numerical analyses, including nuclear and finite element analyses, are utilized to evaluate local TBR, temperature distribution, electromagnetic (EM) forces, load combinations, and stress performance. The results indicate that three cooling capacity enhancement structures are necessary to improve cooling capacity in the multiplier pebble bed area while maintaining the current local TBR. The EM analysis demonstrates that a Maxwell force will constantly act on the WCCB TBM-set, regardless of normal operation or plasma disruption, primarily due to the use of ferromagnetic materials. Furthermore, the structural integrity of the supporter, which provides mechanical support for the TBM and the shield in the WCCB TBM-set, is evaluated under load combinations. Although the current performance of the supporter is inadequate, design modifications may enable it to meet the criteria outlined in RCC-MRx.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115393"},"PeriodicalIF":2.0,"publicationDate":"2025-08-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828604","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
Radioactive waste analysis and disposal following KSTAR device diverter upgrade KSTAR设备分流器升级后的放射性废物分析和处理
IF 2 3区 工程技术
Fusion Engineering and Design Pub Date : 2025-08-12 DOI: 10.1016/j.fusengdes.2025.115342
Hee-Soo. Kim , Young Seok Lee , Kaprai Park , Kwang-Woon Cho , Sung Ill Lee
{"title":"Radioactive waste analysis and disposal following KSTAR device diverter upgrade","authors":"Hee-Soo. Kim ,&nbsp;Young Seok Lee ,&nbsp;Kaprai Park ,&nbsp;Kwang-Woon Cho ,&nbsp;Sung Ill Lee","doi":"10.1016/j.fusengdes.2025.115342","DOIUrl":"10.1016/j.fusengdes.2025.115342","url":null,"abstract":"<div><div>The tokamak device for nuclear fusion experiments consists of various structures. The structure inside the vacuum vessel becomes radioactive due to neutrons generated during the nuclear fusion reaction. The main component of the vacuum vessel is SS316L, and when this material causes a nuclear reaction by neutrons, the main radioactive substances generated are Mn-54, Co-58, and Co-60. Among them, Co-60, with a half-life of 5.3 years, has the longest half-life and greatly affects the radiation dose. In a nuclear reaction caused by neutrons, the radioactive material generated by each structure decays according to its physical half-life and releases radiation. Therefore, when disposed of, they must be treated as radioactive waste, and the disposal plan must reflect the radiation dose and quantity. In addition, graphite tiles contain tritium generated during the nuclear fusion reaction, so this must also be considered. Since this has a significant impact on space and cost, this paper analyzes the results of waste analysis and management according to the replacement of the low diverter of the KSTAR device and plans to utilize it for future device disposal plans.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115342"},"PeriodicalIF":2.0,"publicationDate":"2025-08-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144828167","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
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