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Journal of Fusion Energy最新文献

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Artificial Neural Network-Based Tomography Reconstruction of Plasma Radiation Distribution at GOLEM Tokamak 基于人工神经网络的 GOLEM 托卡马克等离子体辐射分布断层扫描重建技术
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-09-04 DOI: 10.1007/s10894-024-00458-z
S. Abbasi, J. Mlynar, J. Chlum, O. Ficker, V. Svoboda, J. Brotankova
{"title":"Artificial Neural Network-Based Tomography Reconstruction of Plasma Radiation Distribution at GOLEM Tokamak","authors":"S. Abbasi, J. Mlynar, J. Chlum, O. Ficker, V. Svoboda, J. Brotankova","doi":"10.1007/s10894-024-00458-z","DOIUrl":"https://doi.org/10.1007/s10894-024-00458-z","url":null,"abstract":"<p>The paper presents an artificial neural network-based model for tomography reconstruction of visible plasma radiation distribution at the GOLEM tokamak. The model was trained using a dataset from emissivity phantoms and associated synthetic measurements from a poloidal cross-section of the GOLEM tokamak. The model validation was performed on the prediction of various unseen phantom samples with shapes similar to those in the training dataset. The backfit of line-integrated measurements indicates the considerable potential of the proposed model for reconstructing the position, size, shape and intensity of the radiation function of one cross section. Additionally, the neural network-based model offers a significantly shorter prediction time compared to traditional tomography methods, providing a substantial advantage.</p>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142226522","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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 Study on the Reduction of Tritium Breeding Ratio Caused by Inventory Changes of a Solid-State Tritium Breeding Blanket in a Fusion Demonstration Reactor Using MCNP and FISPACT-II 利用 MCNP 和 FISPACT-II 对聚变示范反应堆中固态氚孕育毯库存变化导致的氚孕育率降低进行比较研究
IF 1.9 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-08-08 DOI: 10.1007/s10894-024-00455-2
Byung Chul Kim
{"title":"Comparative Study on the Reduction of Tritium Breeding Ratio Caused by Inventory Changes of a Solid-State Tritium Breeding Blanket in a Fusion Demonstration Reactor Using MCNP and FISPACT-II","authors":"Byung Chul Kim","doi":"10.1007/s10894-024-00455-2","DOIUrl":"https://doi.org/10.1007/s10894-024-00455-2","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141927345","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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 Deuterium Loading on Permeation of Deuterium Through Niobium at Relative Low Pressure 氘负载对相对低压下氘透过铌的影响
IF 1.9 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-07-16 DOI: 10.1007/s10894-024-00448-1
Qi Dan, Ru Tang, Xiaohong Chen
{"title":"Effect of Deuterium Loading on Permeation of Deuterium Through Niobium at Relative Low Pressure","authors":"Qi Dan, Ru Tang, Xiaohong Chen","doi":"10.1007/s10894-024-00448-1","DOIUrl":"https://doi.org/10.1007/s10894-024-00448-1","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141641257","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Deep Learning Based Surrogate Model a fast Soft X-ray (SXR) Tomography on HL-2 a Tokamak 托卡马克 HL-2 上基于深度学习的快速软 X 射线 (SXR) 断层扫描代用模型
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-07-10 DOI: 10.1007/s10894-024-00419-6
Zhijun Wang, Zeyu Zhang, Dong Li, Yixiong Wei, Zongyu Yang, Renjie Yang, Cong Wang, Yunbo Dong
{"title":"Deep Learning Based Surrogate Model a fast Soft X-ray (SXR) Tomography on HL-2 a Tokamak","authors":"Zhijun Wang, Zeyu Zhang, Dong Li, Yixiong Wei, Zongyu Yang, Renjie Yang, Cong Wang, Yunbo Dong","doi":"10.1007/s10894-024-00419-6","DOIUrl":"https://doi.org/10.1007/s10894-024-00419-6","url":null,"abstract":"<p>Tomography is indeed a commonly employed diagnostic technique in fusion campaigns, specifically for determining the shape and position of the plasma. To enhance the accuracy of conventional tomography algorithms, a Bayesian-based non-stationary Gaussian processes tomography as the emission model has been implemented in the soft X-ray diagnostics of the HL-2 A tokamak. However, the Bayesian tomography method is time-consuming and has difficulty achieving quick reconstructions for tokamak. In this work, neural networks have been trained and tested on a large set of sample tomograms based on experimental SXR data and Bayesian tomography method. The trained neural networks can predict the reconstructions of emission profiles accurately, fast, and robustly to noise. In the future, it is possible to easily implement this algorithm on different diagnostics and fusion devices.</p>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141570943","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Retraction Note Investigation of Effects of Toroidal Field Ripple on Plasma Poloidal Beta in IR-T1 Tokamak 环形场波纹对 IR-T1 托卡马克等离子体极坐标β影响的研究
IF 1.9 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-07-08 DOI: 10.1007/s10894-024-00435-6
A. S. Elahi, M. Ghoranneviss
{"title":"Retraction Note Investigation of Effects of Toroidal Field Ripple on Plasma Poloidal Beta in IR-T1 Tokamak","authors":"A. S. Elahi, M. Ghoranneviss","doi":"10.1007/s10894-024-00435-6","DOIUrl":"https://doi.org/10.1007/s10894-024-00435-6","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141668560","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Plasma Breakdown Optimization Calculation Based on Improved Particle Swarm Algorithm for TT-1 Device 基于改进型粒子群算法的 TT-1 设备等离子体击穿优化计算
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-06-26 DOI: 10.1007/s10894-024-00418-7
Shuangbao Shu, Jiaxin Zhang, Shurui Zhang, Jiarong Luo, Shanlin Liu
{"title":"Plasma Breakdown Optimization Calculation Based on Improved Particle Swarm Algorithm for TT-1 Device","authors":"Shuangbao Shu, Jiaxin Zhang, Shurui Zhang, Jiarong Luo, Shanlin Liu","doi":"10.1007/s10894-024-00418-7","DOIUrl":"https://doi.org/10.1007/s10894-024-00418-7","url":null,"abstract":"<p>In the Tokamak discharge experiment, obtaining the largest possible null field region is a necessary condition for the smooth breakdown of the plasma, and adjusting the poloidal field coil current is key to achieving a better null field region. This paper, based on the Sino-Thai Tokamak cooperation project Thailand Tokamak-1 (TT-1) device, employs an exponentially decreasing Particle Swarm Optimization (PSO) algorithm to optimize the poloidal field coil current to create the desired null field region in the vacuum chamber area. First, a calculation model for the mutual inductance coefficient and the null field region is established according to the characteristics and magnetic structure of the TT-1 device, enabling the calculation of the null field region. Then, an optimization model for the poloidal field coil current is established, aiming to create a sufficiently large null field region (less than 10 Gauss) to facilitate breakdown. The optimization is carried out using both a typical linearly decreasing PSO algorithm and an improved PSO algorithm to determine the optimal poloidal field coil current. Compared to the unmodified PSO algorithm, the improved PSO algorithm reduces the root mean square error by 31.80%. The results show that the improved PSO algorithm is more suitable for the optimization of the poloidal field coil, has stronger optimization capabilities, and can effectively create the desired null field region, providing an important reference for the smooth breakdown of plasma in the TT-1 device.</p>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141501727","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Direct Drive Laser Fusion Facility and Pilot Plant 直接驱动激光聚变设施和试验工厂
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-06-18 DOI: 10.1007/s10894-024-00416-9
Malcolm W. McGeoch, Stephen P. Obenschain
{"title":"Direct Drive Laser Fusion Facility and Pilot Plant","authors":"Malcolm W. McGeoch, Stephen P. Obenschain","doi":"10.1007/s10894-024-00416-9","DOIUrl":"https://doi.org/10.1007/s10894-024-00416-9","url":null,"abstract":"<p>Direct-drive laser inertial fusion is a potential producer of baseline power that has increased credibility following the achievement at the National Ignition Facility of ignition and net gain using indirect-drive via laser-produced X-rays. Ultraviolet broad band lasers such as argon fluoride, at 193 nm and 10 THz, are predicted by hydrocode simulations to enable energy gains greater than 100 with laser energies less than 0.5 MJ, stimulating renewed reactor design effort in anticipation of experimental verification. The present study attempts to create a reactor design with very few unknowns in materials, corrosion, first wall viability, tritium breeding and ease of servicing. A new variant of magnetic intervention has an increased ion dump surface area combined with a simple structure. Around an inner vacuum vessel an all-ceramic tritium breeder blanket is possible in an unconstrained volume, allowing helium coolant to be used without excessive pressure or flow power. The case is made for development of a lead (Pb) ceramic as the neutron multiplier.</p>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141501798","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Risk-Aware Framework Development for Disruption Prediction: Alcator C-Mod and DIII-D Survival Analysis 用于中断预测的风险意识框架开发：Alcator C-Mod 和 DIII-D 生存分析
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-06-10 DOI: 10.1007/s10894-024-00413-y
Zander Keith, Chirag Nagpal, Cristina Rea, R. A. Tinguely
{"title":"Risk-Aware Framework Development for Disruption Prediction: Alcator C-Mod and DIII-D Survival Analysis","authors":"Zander Keith, Chirag Nagpal, Cristina Rea, R. A. Tinguely","doi":"10.1007/s10894-024-00413-y","DOIUrl":"https://doi.org/10.1007/s10894-024-00413-y","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141363462","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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: 1
The IFMIF-DONES Diagnostics and Control Systems: Current Design Status, Integration Issues and Future Perspectives Embedding Artificial Intelligence Tools IFMIF-DONES 诊断和控制系统：嵌入人工智能工具的设计现状、集成问题和未来展望
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-06-10 DOI: 10.1007/s10894-024-00414-x
M. Cappelli, C. Torregrosa-Martin, J. Diaz, A. Ibarra
{"title":"The IFMIF-DONES Diagnostics and Control Systems: Current Design Status, Integration Issues and Future Perspectives Embedding Artificial Intelligence Tools","authors":"M. Cappelli, C. Torregrosa-Martin, J. Diaz, A. Ibarra","doi":"10.1007/s10894-024-00414-x","DOIUrl":"https://doi.org/10.1007/s10894-024-00414-x","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141361496","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
The Investigation of Pre-ionization Effect on the Improvement of Pinch Quality and Increased Hard X-ray Radiation in a Dense Plasma Focus (DPF) Device 研究预电离对改善密集等离子体聚焦（DPF）装置的夹持质量和增加硬 X 射线辐射的影响
IF 1.1 4区 工程技术
Journal of Fusion Energy Pub Date : 2024-06-09 DOI: 10.1007/s10894-024-00415-w
Abdolhadi Hosseinzadeh, N. Vosoughi, T. D. Mahabadi, D. Piriaei
{"title":"The Investigation of Pre-ionization Effect on the Improvement of Pinch Quality and Increased Hard X-ray Radiation in a Dense Plasma Focus (DPF) Device","authors":"Abdolhadi Hosseinzadeh, N. Vosoughi, T. D. Mahabadi, D. Piriaei","doi":"10.1007/s10894-024-00415-w","DOIUrl":"https://doi.org/10.1007/s10894-024-00415-w","url":null,"abstract":"","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.1,"publicationDate":"2024-06-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141368343","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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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