Journal of Fusion Energy最新文献_第2页

Retraction Note: Measurements of the Plasma Current Density and Q-Profiles in IR-T1 Tokamak 注：IR-T1托卡马克中等离子体电流密度和q曲线的测量

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-18 DOI: 10.1007/s10894-025-00487-2

M. Ghoranneviss, A. Salar Elahi, A. Abbaspour Tehrani Fard, M. Tajdidzadeh

引用次数: 0

Study on Phased Array Ultrasonic Testing Techniques for Austenitic Stainless Steel Butt Welds 奥氏体不锈钢对接焊缝相控阵超声检测技术研究

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-17 DOI: 10.1007/s10894-025-00475-6

Chengwen Li, Rui wang, Zhihong Liu, Haibiao Ji, Shijun Qin, Ren Chen, Yaqi Zhong, Huapeng Wu

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Scaling Analysis on In-VV LOCA for the Experimental Facility of Water-Cooled Components in CFETR CFETR水冷件实验装置vv内LOCA结垢分析

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-15 DOI: 10.1007/s10894-025-00480-9

Qixin Ling, Songlin Liu

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Thermal Response of a Lithium Vapor Divertor to Cyclical Operation 锂蒸汽分流器对循环运行的热响应

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-14 DOI: 10.1007/s10894-025-00479-2

Matthew S. Parsons, Margaret Porcelli, Eric D. Emdee, Robert J. Goldston

{"title":"Thermal Response of a Lithium Vapor Divertor to Cyclical Operation","authors":"Matthew S. Parsons, Margaret Porcelli, Eric D. Emdee, Robert J. Goldston","doi":"10.1007/s10894-025-00479-2","DOIUrl":"10.1007/s10894-025-00479-2","url":null,"abstract":"<div>The lithium vapor divertor concept is being developed as a method to achieve detached divertor conditions in a tokamak while minimizing impurity radiation losses from the core plasma. SOLPS-ITER modeling has previously been used to identify some of the geometric constraints and required lithium evaporation rate of a lithium vapor divertor in a medium-sized tokamak during steady-state operation. Here an updated conceptual design based on these operating requirements is introduced and the thermal response of the system is modeled during cyclical operation, consistent with operation in a short-pulse tokamak. Controllability of the temperature of the lithium capillary porous system (CPS) is achieved by adopting a design where there is no line-of-sight for radiation from the plasma to reach the heated CPS surface. Operational strategies to minimize the amount of lithium evaporated between plasma discharges while achieving steady evaporation rates during plasma discharges are discussed and modeled here. The optimal feedforward control strategy demonstrated in this work is to ramp up the temperature of the evaporator as quickly as possible immediately before a plasma discharge and then reduce the heating to match the desired steady-state net evaporation rate just before the plasma discharge begins, allowing the thermal inertia of the system to stabilize the evaporation rate during the first second of the plasma discharge.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00479-2.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143423233","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

Retraction Note: Effects of Resonant Helical Field (RHF) on Equilibrium Properties of IR-T1 Tokamak Plasma 共振螺旋场（RHF）对IR-T1托卡马克等离子体平衡特性的影响

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-12 DOI: 10.1007/s10894-025-00482-7

A. Salar Elahi, M. Ghoranneviss

引用次数: 0

Retraction Note: Estimating Time Dependence of Edge Plasma Turbulence in IR-T1 Tokamak 注：估计IR-T1托卡马克中边缘等离子体湍流的时间依赖性

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-10 DOI: 10.1007/s10894-025-00485-4

K. Mikaili Agah, M. Ghoranneviss, M. K. Salem, A. Salar Elahi, S. Mohammadi, R. Arvin

引用次数: 0

Role of E × B Drift in Divertor Detachment Control via Boron Powder Injection on EAST 硼粉注入对东侧导流器脱离控制的作用

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-10 DOI: 10.1007/s10894-025-00477-4

Lei Peng, Zhen Sun, Jizhong Sun, Rajesh Maingi, Guozhang Jia, Xavier Bonnin, Fang Gao, GuiZhong Zuo, Wei Xu, Weikang Wang, Jinyuan Liu

{"title":"Role of E × B Drift in Divertor Detachment Control via Boron Powder Injection on EAST","authors":"Lei Peng, Zhen Sun, Jizhong Sun, Rajesh Maingi, Guozhang Jia, Xavier Bonnin, Fang Gao, GuiZhong Zuo, Wei Xu, Weikang Wang, Jinyuan Liu","doi":"10.1007/s10894-025-00477-4","DOIUrl":"10.1007/s10894-025-00477-4","url":null,"abstract":"<div>The effects of B powder injection on plasma detachment about EAST discharge were studied by using SOLPS-ITER code package with the effects of E × B drifts considered. The simulation results show that plasma detachment occurs at the inner target in favourable toroidal magnetic field (Bt) direction at a relatively low B powder flow rate, one order of magnitude lower than that at the outer target. In a similar scenario with unfavourable Bt, it is found that the detachment thresholds of B flow rate for both the inner and outer targets are close and of the same order as that for the outer target with favourable Bt. In favourable Bt direction at B powder flow rate of 1.2 × 1021 atoms/s, a localized, broadened high-density region is formed near the inner target benefitted by the injection location and the E × B drift, and a radiation-intensified zone, mostly contributed by B1+ and B2+, occurs there. The E × B drift facilitates plasma detachment at the inner target and simultaneously amplifies the in–out divertor asymmetry. In addition, the simulation results with three different injection locations show that the injection from outer strike point leads to the lowest Zeff inside the separatrix and has an intermediate flow rate for detachment at the outer target, comparing with the X-point and upstream locations.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143379839","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 Tokamak Plasma MHD Activity Using FFT Analysis of Mirnov Coils Oscillations 利用FFT分析Mirnov线圈振荡研究托卡马克等离子体MHD活性

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-08 DOI: 10.1007/s10894-025-00483-6

Z. Goodarzi, M. Ghoranneviss, A. Salar Elahi

引用次数: 0

Retraction Note: Effect of Resonant Helical Field (RHF) on Runaway Electrons in Tokamaks 注：共振螺旋场对托卡马克中失控电子的影响

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-08 DOI: 10.1007/s10894-025-00484-5

M. R. Ghanbari, M. Ghoranneviss, K. Ghanbari, A. Salar Elahi, M. K. Salem, S. Mohammadi, R. Arvin

引用次数: 0

Power Balance of the Quasi-Stationary Stagnation Phase of Superdense Boron-Proton Plasma 超致密硼质子等离子体准静止停滞相的功率平衡

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-04 DOI: 10.1007/s10894-025-00478-3

Alexei Yu. Chirkov, Evgeny G. Vovkivsky

{"title":"Power Balance of the Quasi-Stationary Stagnation Phase of Superdense Boron-Proton Plasma","authors":"Alexei Yu. Chirkov, Evgeny G. Vovkivsky","doi":"10.1007/s10894-025-00478-3","DOIUrl":"10.1007/s10894-025-00478-3","url":null,"abstract":"<div>The features of high-gain aneutronic p–11B fusion are examined. A comparison of inertial systems with extremely high plasma densities (n ~ 1030–1031 m–3) and stationary systems with magnetic confinement of low-density plasma (n ~ 1020–1022 m–3) shows that it is also necessary to analyze combined schemes based on magneto-inertial systems with fuel refill. Present work considers limiting modes of the quasi-stationary phase of fusion, which show the maximum plasma gain at plasma density n ~ 1031 m–3 and ion temperatures Ti ~ 200 keV, electron temperatures Te ~ 100 keV at the beginning of the quasi-stationary phase. The content of reaction products (α-particles) has a significant influence on the parameters of the system. If the confinement time of α-particles is the same as for the fuel components, then due to radiation the energy gain Q ~ 1. In modes with a reduced confinement time of α-particles, the gain reaches a value of Q ~ 6. A further increase in Q requires extremely high plasma energy.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143107976","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