Journal of Fusion Energy最新文献_第6页

Retraction Note: Fast Electrons Behavior in Presence of External Radial Electric Field in IR-T1 Tokamak 撤回说明：IR-T1 托卡马克中存在外部径向电场时的快速电子行为

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-07-02 DOI: 10.1007/s10894-024-00428-5

A. Salar Elahi, M. Ghoranneviss

引用次数: 0

Retraction Note to: Theoretical and experimental approach in poloidal beta and internal inductance measurement on IR-T1 tokamak 撤回说明：IR-T1 托卡马克上极性贝塔和内电感测量的理论和实验方法

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-07-02 DOI: 10.1007/s10894-024-00430-x

A. Salar Elahi, M. Ghoranneviss, M. Emami, A. Rahimi Rad

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 1.9 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":"10.1007/s10894-024-00418-7","url":null,"abstract":"<div><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></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"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 1.9 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

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 1.9 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. Alex 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. Alex Tinguely","doi":"10.1007/s10894-024-00413-y","DOIUrl":"10.1007/s10894-024-00413-y","url":null,"abstract":"<div><p>Survival regression models can achieve longer warning times at similar receiver operating characteristic performance than previously investigated models. Survival regression models are also shown to predict the time until a disruption will occur with lower error than other predictors. Time-to-event predictions from time-series data can be obtained with a survival analysis statistical framework, and there have been many tools developed for this task which we aim to apply to disruption prediction. Using the open-source Auton-Survival package we have implemented disruption predictors with the survival regression models Cox Proportional Hazards, Deep Cox Proportional Hazards, and Deep Survival Machines. To compare with previous work, we also include predictors using a Random Forest binary classifier, and a conditional Kaplan-Meier formalism. We benchmarked the performance of these five predictors using experimental data from the Alcator C-Mod and DIII-D tokamaks by simulating alarms on each individual shot. We find that developing machine-relevant metrics to evaluate models is an important area for future work. While this study finds cases where disruptive conditions are not predicted, there are instances where the desired outcome is produced. Giving the plasma control system the expected time-to-disruption will allow it to determine the optimal actuator response in real time to minimize risk of damage to the device.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00413-y.pdf","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":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

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 1.9 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":"10.1007/s10894-024-00414-x","url":null,"abstract":"<div><p>As an integral part of the European strategy for advancing fusion-generated electricity, IFMIF-DONES represents a high-intensity neutron irradiation plant with the main purpose of assessing the suitability of materials for fusion reactor applications. Its primary mission is to examine how materials respond to irradiation within a neutron flux that mimics the conditions expected in the first wall of the proposed DEMO reactor, which is intended to succeed ITER. Consequently, IFMIF-DONES, whose construction is slated to commence shortly, plays a pivotal role in aiding the development, approval, and safe operation of DEMO, as well as future fusion power plants. This paper provides a quick overview of the current development of the IFMIF-DONES neutron source with a particular snapshot of the present engineering design status for what concerns the instrumentation and control systems together with its complex diagnostics, that guarantees the safe monitoring, supervision and regulation of all operations. The current status of design, after the completion of the preliminary design phase is presented, as well as the existing and future plans for their integration also using some of the new capabilities offered by Artificial Intelligence tools.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00414-x.pdf","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":"OA","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 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-06-09 DOI: 10.1007/s10894-024-00415-w

Abdolhadi Hosseinzadeh, Naser 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, Naser Vosoughi, T. D. Mahabadi, D. Piriaei","doi":"10.1007/s10894-024-00415-w","DOIUrl":"10.1007/s10894-024-00415-w","url":null,"abstract":"<div><p>This study delves into the impact of the pre-ionization technique, facilitated by an optimal shunt resistor, on a DPF device operating with deuterium gas. The investigation unveils enhancements in critical parameters within the plasma column environment during the pinch phase, specifically the total and plasmoid hard x-ray yields. Employing a combination of time-resolved detectors, such as plastic scintillator and magnetic probe arrays, alongside time-integrated detectors like pinhole camera, and just by using this technique, the research illustrated an augmented plasma sheath velocity during the axial phase. Notably and other than the enhancement of hard x-ray yield, the optimal pressure of DPF device experienced an upward shift to higher working points, accompanied by a reduction in deviation from the optimum point (52.7% and 66.6% for total and plasmoid hard x-rays respectively). This, in turn, bolstered the Lawson criterion, impacting both particle density and temperature in the plasma column. A nuanced examination further discerned that, while the pre-ionization technique amplified the intensities of total and plasmoid hard x-rays, it maintained a consistent contribution to the emitted hard x-ray intensity from the device, refraining from establishing clear superiority between these two kinds of hard x-rays, with or without using the shunt resistor.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9,"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

Degenerate Pile-up Correction in Pulse Height Spectra from Gamma-ray Spectrometers 伽马射线光谱仪脉冲高度光谱中的退化堆积校正

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-05-22 DOI: 10.1007/s10894-024-00409-8

Giulia Marcer, Andrea Dal Molin, Marica Rebai, Davide Rigamonti, Marco Tardocchi

{"title":"Degenerate Pile-up Correction in Pulse Height Spectra from Gamma-ray Spectrometers","authors":"Giulia Marcer, Andrea Dal Molin, Marica Rebai, Davide Rigamonti, Marco Tardocchi","doi":"10.1007/s10894-024-00409-8","DOIUrl":"10.1007/s10894-024-00409-8","url":null,"abstract":"<div><p>One of the primary obstacles faced by spectrometers operating under high counting rates is pile-up, which occurs when two or more events are detected within a timelapse short enough to result in a superposition of the events waveforms. These can not hence be integrated separately in order to get their amplitudes. Piled-up events are typically identified using pile-up rejection or recovery algorithms. In the latter case, the constituent single waveforms and their amplitudes are also restored. However, there are instances in which the pulses overlap so closely that it is impossible to identify the occurrence of pile-up, resulting in the integration of these pulses into a single spurious event. This phenomenon is known as degenerate pile-up. A method to rectify the incorrect reconstruction of degenerate pile-up was developed, based on a statistical approach, which can be directly applied to the pulse height spectra distributions. The approach was tested on a number of synthetic spectra, with counting rates ranging from 20 kHz up to 1 MHz. The recovered spectra were compared to those purely analysed with a pile-up recovery algorithm, demonstrating an improvement of the reconstructed spectrum of several tens of percent when compared to the true synthetic counterpart.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-05-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00409-8.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141109309","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Symmetrized Dot Pattern as an Alternative Method to Visualize the Dynamics of Tokamak Plasma Radiation 对称点图案作为托卡马克等离子体辐射动态可视化的一种替代方法

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-05-22 DOI: 10.1007/s10894-024-00410-1

Agnieszka Jardin, Axel Jardin, the WEST Team

引用次数: 0

Preliminary Design of Water-Cooling System for Liquid Metal Divertor Target Test Module in EAST EAST 中液态金属憩室靶测试模块水冷系统的初步设计

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-05-21 DOI: 10.1007/s10894-024-00412-z

Siyao Wang, Zhe Sun, Xinyuan Qian, Xuebing Peng

{"title":"Preliminary Design of Water-Cooling System for Liquid Metal Divertor Target Test Module in EAST","authors":"Siyao Wang, Zhe Sun, Xinyuan Qian, Xuebing Peng","doi":"10.1007/s10894-024-00412-z","DOIUrl":"10.1007/s10894-024-00412-z","url":null,"abstract":"<div><p>Developing a robust, feasible, and reliable plasma-facing components (PFCs) is a key mission to realize the commercial fusion power reactor. The situation of the divertor targets will be particularly severe because of higher heat and particle flux in the future devices. In order to improve the power handling capacity and lifetime of the divertor target, a solution of covering the plasma-facing surface of the target with liquid metal was proposed owing to the ability of self-healing. However, liquid metal targets are still in early stages of development and there are many issues need to be explored, especially in the context of the plasma environment in a tokamak. Experimental Advanced Superconducting Tokamak (EAST), aiming to investigate scientific and engineering issues for fusion, provides a suitable environment to study the performance of liquid metal divertor. In this paper, the design of a water-cooling system for liquid metal divertor target test module in EAST is presented. It contains four circulation loops to deal with different accidents to ensure enough safety margin while minimizing the impact on the plasma discharge experiment. The corresponding system safety analyses have been performed and verified that the water-cooling system can meet the design requirements for the liquid metal target test under both normal condition and accidental events. Furthermore, the design of the water-cooling system is compatible with the constraints adopted for the high heat flux components, enhancing its potential for serving other test modules with similar water-cooling requirements in EAST.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-05-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141116980","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