Fusion Engineering and Design最新文献

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Nuclear data uncertainty in 14C production from oxygen isotopes 氧同位素产生 14C 的核数据不确定性
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-18 DOI: 10.1016/j.fusengdes.2024.114708
Priti Kanth, Ivan Kodeli, Mark R. Gilbert
{"title":"Nuclear data uncertainty in 14C production from oxygen isotopes","authors":"Priti Kanth,&nbsp;Ivan Kodeli,&nbsp;Mark R. Gilbert","doi":"10.1016/j.fusengdes.2024.114708","DOIUrl":"10.1016/j.fusengdes.2024.114708","url":null,"abstract":"<div><div><sup>14</sup>C is produced from the reactions of O isotopes with high-energy neutrons. Due to its long half-life, high residence time in the environment and ease of assimilation into living matter, the production of <sup>14</sup>C is a major concern when planning for the transportation and disposal of radioactive materials. Observed variation in calculated <sup>14</sup>C production from O isotopes using different data libraries causes uncertainties that are demonstrated to affect predictions of radioactive waste arisings and thus could impact disposal and recycling recommendations. There are also significant inconsistencies in the uncertainty data and co-variance matrices given in the nuclear data files for O isotopes.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"210 ","pages":"Article 114708"},"PeriodicalIF":1.9,"publicationDate":"2024-11-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142701011","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Development of a heated liquid Sn flowing system and preliminary results of wettability improvement by inter-metallic layer 加热液态 Sn 流动系统的开发以及金属间层改善润湿性的初步结果
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-18 DOI: 10.1016/j.fusengdes.2024.114727
Yukinori Hamaji , Yuki Hayashi , Suguru Masuzaki
{"title":"Development of a heated liquid Sn flowing system and preliminary results of wettability improvement by inter-metallic layer","authors":"Yukinori Hamaji ,&nbsp;Yuki Hayashi ,&nbsp;Suguru Masuzaki","doi":"10.1016/j.fusengdes.2024.114727","DOIUrl":"10.1016/j.fusengdes.2024.114727","url":null,"abstract":"<div><div>A new gas-driven liquid metal (Sn) flow device named Gas-driven Liquid-metal Flow test device (GaLF) was established. The device is a pilot device for a linear plasma device that irradiates flowing liquid metal (LM) free-surface. The flow rate of Sn controlled by the inlet gas rate was evaluated by comparison with the weight change of the downstream Sn tank. A new method to achieve better wettability against liquid Sn by forming an intermetallic layer was suggested and tested in GaLF. The treated stainless steel showed better wettability enough to achieve a good free surface flow for plasma-surface interaction studies.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"210 ","pages":"Article 114727"},"PeriodicalIF":1.9,"publicationDate":"2024-11-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142701012","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
Formation, characterization and deuterium permeation of Al2O3/Fe-Al layers on SS-316L surface SS-316L 表面 Al2O3/Fe-Al 层的形成、表征和氘渗透
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-16 DOI: 10.1016/j.fusengdes.2024.114735
Feilong Yang, Xin Xiang, Chang'an Chen, Li Hu, Ce Ma, Guikai Zhang, Yaqi Song
{"title":"Formation, characterization and deuterium permeation of Al2O3/Fe-Al layers on SS-316L surface","authors":"Feilong Yang,&nbsp;Xin Xiang,&nbsp;Chang'an Chen,&nbsp;Li Hu,&nbsp;Ce Ma,&nbsp;Guikai Zhang,&nbsp;Yaqi Song","doi":"10.1016/j.fusengdes.2024.114735","DOIUrl":"10.1016/j.fusengdes.2024.114735","url":null,"abstract":"<div><div>316L austenitic stainless steel (SS-316L) is the most promising candidate structural material facing tritium in fusion reactors. However, tritium permeation of SS-316L at high temperatures will lead to loss of tritium, which ultimately generates radiological hazards and challenges tritium self-sufficiency. Preparing tritium permeation barriers (TPBs) on SS-316L surfaces is a critical way to solve this problem. In this study, Al<sub>2</sub>O<sub>3</sub>/Fe-Al coatings were applied to the SS-316L surface through an \"aluminizing + oxidation\" process, followed by a detailed analysis of the microstructures and their deuterium-resistant properties. Results delivered that the prepared coating structure comprises a 10-micron-thick Fe-Al transition layer and a dense hundred-nanometer-thick Al<sub>2</sub>O<sub>3</sub> film. The deuterium resistance of the coating is ranking, where the deuterium permeability can be reduced by three orders of magnitude at 500 °C.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114735"},"PeriodicalIF":1.9,"publicationDate":"2024-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655550","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
Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution 三种大气扩散模型在预测近地表氚浓度分布方面的性能
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-16 DOI: 10.1016/j.fusengdes.2024.114728
Yiling Ran , Yuxuan Wang , Baojie Nie , Chunlei Su , Zhiming Li , Dezhong Wang
{"title":"Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution","authors":"Yiling Ran ,&nbsp;Yuxuan Wang ,&nbsp;Baojie Nie ,&nbsp;Chunlei Su ,&nbsp;Zhiming Li ,&nbsp;Dezhong Wang","doi":"10.1016/j.fusengdes.2024.114728","DOIUrl":"10.1016/j.fusengdes.2024.114728","url":null,"abstract":"<div><div>Tritium discharge from the fusion system and its environmental impact receive wide attention. Considerable deviation exists in various atmospheric dispersion models for evaluating near-surface tritium concentration distribution. To quantitatively find out the diversity of these models, a performances comparison was performed based on the case of tritium discharge from the ITER site. Wind tunnel experiments were preliminarily performed to test the performances of these models. Annual average tritium concentration and individual radiation dose were assessed for some selected residential areas adjacent to the ITER site. It is indicated that atmospheric dispersion simulation by the CFD method is significantly influenced by the modeling of the turbulence. Atmospheric dispersion predicted by the CFD-RANS model with default parameters is weaker, resulting in higher downwind pollutant concentration, compared with the CFD-LES model, Gaussian plume model and Lagrangian puff model. Wind tunnel experimental results relatively support the CFD-LES model with strong turbulent dispersion. CFD-LES model is superior in reflecting the effects of complex topography in high resolution and shows strong turbulent dispersion. Individual radiation dose under normal operation at selected residential areas near ITER was estimated to be much lower than the natural radiation level and also the ITER dose limit even considering the uncertainty margin.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114728"},"PeriodicalIF":1.9,"publicationDate":"2024-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655548","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
Neutron transport and activation comparison between OpenMC and FISPACT-II in ARC-class reactor OpenMC 和 FISPACT-II 在 ARC 级反应堆中的中子输运和活化比较
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-16 DOI: 10.1016/j.fusengdes.2024.114713
Davide Pettinari , Raffaella Testoni , Massimo Zucchetti , Miriam Parisi
{"title":"Neutron transport and activation comparison between OpenMC and FISPACT-II in ARC-class reactor","authors":"Davide Pettinari ,&nbsp;Raffaella Testoni ,&nbsp;Massimo Zucchetti ,&nbsp;Miriam Parisi","doi":"10.1016/j.fusengdes.2024.114713","DOIUrl":"10.1016/j.fusengdes.2024.114713","url":null,"abstract":"<div><div>In a fusion reactor, high-energy neutron fluxes strike the materials causing radiation damage and triggering nuclear reactions that alter the chemical composition of the materials through transmutation. This investigation employs the Monte Carlo code OpenMC with Direct Accelerated Geometry Monte Carlo (DAGMC), a software package that allows users to perform Monte Carlo radiation transport directly on CAD models. The analysis was conducted on an Affordable Robust Compact (ARC) class reactor using a 3D CAD geometry. OpenMC supports depletion calculations allowing for the time evolution of the radioactive inventories evaluation. This study focuses on the machine’s nuclear performance, analyzing tritium production, neutron fluxes, and power deposition to assess the reactor’s behavior. It also explores the primary aspects of neutron irradiation on solid materials in the ARC class reactor, with particular emphasis on neutron-induced activation and displacements per atom (DPA). The neutronic results indicate that the predicted tritium breeding ratio and power density are consistent with both the reactor design specifications and the findings in existing literature, while the DPA and activation calculations reveal key areas of material degradation due to neutron irradiation. To validate the accuracy of the results, a comparison was made with corresponding results obtained using the FISPACT-II code. The agreement between the two codes serves as a benchmark for the reliability of OpenMC in predicting nuclear activation phenomena in fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114713"},"PeriodicalIF":1.9,"publicationDate":"2024-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655547","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Numerical study of dynamic behavior of beryllium pebble under perturbation of electromagnetic field in fusion blanket 聚变毯中电磁场扰动下铍卵石动态行为的数值研究
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-16 DOI: 10.1016/j.fusengdes.2024.114730
Wang Jian , Tang Zhengquan , Liu Mingzong , Lei Mingzhun , Deng Haishun
{"title":"Numerical study of dynamic behavior of beryllium pebble under perturbation of electromagnetic field in fusion blanket","authors":"Wang Jian ,&nbsp;Tang Zhengquan ,&nbsp;Liu Mingzong ,&nbsp;Lei Mingzhun ,&nbsp;Deng Haishun","doi":"10.1016/j.fusengdes.2024.114730","DOIUrl":"10.1016/j.fusengdes.2024.114730","url":null,"abstract":"<div><div>The fusion blanket system is a core component of fusion reactors, however the operational environment of it is notably harsh, characterized by strong magnetic fields, high heat fluxes, and intense radiation exposure. It is subjected to considerable thermal, mechanical, and electromagnetic stresses, particularly during plasma transient events. Consequently, an in-depth investigation into the safety of the blanket system under electromagnetic stress conditions is imperative. The present study focuses on a solid blanket configuration featuring a beryllium pebble bed. The study explores the dynamics of particle systems influenced by magnetic forces, formulates a comprehensive mathematical and physical model for particle systems within magnetic fields, constructs a pebble bed for particles under magnetic conditions, and scrutinizes the fundamental behavior of the beryllium pebble bed in the face of magnetic perturbations. This research contributes essential parameters and data pertinent to the design of the pebble bed in fusion devices.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114730"},"PeriodicalIF":1.9,"publicationDate":"2024-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655549","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
Infrared spectral emissivities of CN-HCCB-TBM structural materials CN-HCCB-TBM 结构材料的红外光谱发射率
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-15 DOI: 10.1016/j.fusengdes.2024.114710
Leran Liu , Guoping Yang , Junshan Wan , Hongbin Liao , Jialin Gong , Xinghua Wu , Longfei Li , Yufang Liu , Zaixin Li , Long Zhang , Xiaoyu Wang
{"title":"Infrared spectral emissivities of CN-HCCB-TBM structural materials","authors":"Leran Liu ,&nbsp;Guoping Yang ,&nbsp;Junshan Wan ,&nbsp;Hongbin Liao ,&nbsp;Jialin Gong ,&nbsp;Xinghua Wu ,&nbsp;Longfei Li ,&nbsp;Yufang Liu ,&nbsp;Zaixin Li ,&nbsp;Long Zhang ,&nbsp;Xiaoyu Wang","doi":"10.1016/j.fusengdes.2024.114710","DOIUrl":"10.1016/j.fusengdes.2024.114710","url":null,"abstract":"<div><div>The Infrared spectral emissivity tests were conducted from 523 K to 923 K and from 473 K to 873 K on Chinese low-activation ferritic/martensitic steel (CLF-1) and 316L(N)-IG, separately to support radiation heat transfer analysis of the Chinese Helium-Cooled Ceramic Breeder Test Blanket Module (CN-HCCB-TBM) and improve fusion-materials database. A rapid emissivity test method was utilised. The total hemispherical emissivities of these two materials were calculated using numerical integration, with values of 0.16 (523 K), 0.19 (623 K), 0.21 (723 K), 0.23 (823 K), and 0.26 (923 K) found for CLF-1, and 0.10 (473 K), 0.13 (573 K), 0.14 (673 K), 0.14 (773 K), and 0.15 (873 K) found for 316L(N)-IG. A comparison of the emissivity results for CLF-1 and Eurofer97 showed that they were in agreement.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114710"},"PeriodicalIF":1.9,"publicationDate":"2024-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655546","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
Energetics of vacancy clusters in TiVTaW low-activation high-entropy alloy investigated by ab initio calculations 通过 ab initio 计算研究 TiVTaW 低活化高熵合金中空位团簇的能动性
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-14 DOI: 10.1016/j.fusengdes.2024.114711
Yuji Harada, Katsuaki Tanabe
{"title":"Energetics of vacancy clusters in TiVTaW low-activation high-entropy alloy investigated by ab initio calculations","authors":"Yuji Harada,&nbsp;Katsuaki Tanabe","doi":"10.1016/j.fusengdes.2024.114711","DOIUrl":"10.1016/j.fusengdes.2024.114711","url":null,"abstract":"<div><div>High-entropy alloys (HEAs) have attracted attention as potential candidates for nuclear fusion reactor materials due to their superior mechanical properties and irradiation resistance. The TiVTaW low-activation HEA exhibits an especially large variation in the cohesive energies of the pure metals of its alloying elements, leading to the characteristic of energetically heterogeneous atomic environments that differ at each atomic site, a focal point of this study. To evaluate the influence of this site-to-site variation on vacancy cluster formation, in this study, density functional theory calculations were conducted on small vacancy clusters consisting of the nearest neighbor configurations in equimolar TiVTaW. The monovacancy formation energies in TiVTaW were found to span a significantly broader range compared to those in other HEAs. Moreover, the range of vacancy cluster formation energies in TiVTaW was observed to be nearly identical to the range of the vacancy cluster formation energies of its alloying elements in the pure metals. Our calculations also showed that clusters with five or fewer vacancies exhibit a lower mean binding energy compared to the pure metals of the alloying elements, indicating that vacancy clusters in TiVTaW are less stable than those in pure metals. Additionally, the distribution of cluster binding energies for sizes less than five-vacancy clusters was found to range from −1.60 to 3.12 eV, which includes unstable clusters with negative binding energies. These energetic characteristics arising from the heterogeneous atomic environments unique to HEAs can influence void nucleation under irradiation. Furthermore, based on a thermodynamic model, local maxima in the free energy change correlating with cluster size were observed during the nucleation of vacancy clusters, indicating the generation of metastable small vacancy clusters. These findings provide a new perspective on irradiation damage mechanisms in general HEAs.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114711"},"PeriodicalIF":1.9,"publicationDate":"2024-11-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655545","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
Nano-sized high-entropy oxide dispersoids for achieving high strength and thermal stability in tungsten alloys 用于实现钨合金高强度和热稳定性的纳米级高熵氧化物分散体
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-13 DOI: 10.1016/j.fusengdes.2024.114712
M.L. Yu , Z.M. Xie , X.F. Xie , W.B. Jiang , X. Dang , Z.L. Huang , Y.G. Zhang , R. Liu , X.B. Wu , C.S. Liu , Q.F. Fang
{"title":"Nano-sized high-entropy oxide dispersoids for achieving high strength and thermal stability in tungsten alloys","authors":"M.L. Yu ,&nbsp;Z.M. Xie ,&nbsp;X.F. Xie ,&nbsp;W.B. Jiang ,&nbsp;X. Dang ,&nbsp;Z.L. Huang ,&nbsp;Y.G. Zhang ,&nbsp;R. Liu ,&nbsp;X.B. Wu ,&nbsp;C.S. Liu ,&nbsp;Q.F. Fang","doi":"10.1016/j.fusengdes.2024.114712","DOIUrl":"10.1016/j.fusengdes.2024.114712","url":null,"abstract":"<div><div>In this paper, pure W, W-0.8wt % (HfNbMoZrTi)B<sub>2</sub> and W-1.0wt % (HfNbMoZrTi)B<sub>2</sub> (abbreviated as W-0.8HEB and W-1.0HEB, respectively) materials were fabricated using mechanical ball milling and spark plasma sintering. The effects of HEB addition on the microstructure, mechanical properties, and thermal conductivity were studied. The W-0.8HEB materials demonstrated a high hardness of approximately 506 Hv and a high yield strength of 1774 MPa, surpassing those of pure W and W-1.0HEB. Additionally, the recrystallization temperature of W-0.8HEB reached up to 1800 °C, higher than that of most reported W materials. HRTEM results revealed highly stable, nanosized, brookite-structured (HfNbMoZrTi)O<sub>2</sub> particles formed by an in-situ reaction between (HfNbMoZrTi)B<sub>2</sub> and O impurities during high-temperature sintering. This reaction diminishes the interstitial O concentration in W, resulting in enhanced mechanical properties and thermal stability.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114712"},"PeriodicalIF":1.9,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655648","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
Research on deformation prediction of CFETR multi-purpose overloaded robot based on real-time structural simulator 基于实时结构模拟器的 CFETR 多用途超载机器人变形预测研究
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-11-13 DOI: 10.1016/j.fusengdes.2024.114709
Zhixin Yao , Guodong Qin , Muquan Wu , Congju Zuo , Tao Zhang
{"title":"Research on deformation prediction of CFETR multi-purpose overloaded robot based on real-time structural simulator","authors":"Zhixin Yao ,&nbsp;Guodong Qin ,&nbsp;Muquan Wu ,&nbsp;Congju Zuo ,&nbsp;Tao Zhang","doi":"10.1016/j.fusengdes.2024.114709","DOIUrl":"10.1016/j.fusengdes.2024.114709","url":null,"abstract":"<div><div>The CFETR Multi-Purpose Overload Robot (CMOR) is a key subsystem of the China Fusion Engineering Test Reactor (CFETR), which can perform maintenance tasks of the internal components. However, the large slenderness ratio of the structure results in low control accuracy of the CMOR end-effector. This paper proposes a CMOR deformation prediction method based on the real-time structural simulator. The overall deformation model of CMOR is analyzed based on the single joint deformation mechanism. Based on the principle of layered control, the control framework of the CMOR structural simulator is constructed, and the deformation data of CMOR in different positions are calculated based on the finite element method. A hybrid neural network containing a multilayer perceptron, transformer, and attention mechanism is designed to train the CMOR deformation prediction model. The training results show that the deformation prediction model converges quickly and fits the deformation of the CMOR structure well with small prediction errors. Finally, the real-time structure simulator is developed based on the deformation prediction model, and the deformation of CMOR is reconstructed with the update frequency of 2 Hz and the absolute error at any point within ±10 mm, which verifies the correctness of the CMOR structural deformation prediction method.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"209 ","pages":"Article 114709"},"PeriodicalIF":1.9,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142655585","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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