Journal of Fusion Energy最新文献_第2页

Study on Corrosion Behavior of 3D-Printing W and WZrC in Static Liquid Li 3d打印W和WZrC在静态液体Li中的腐蚀行为研究

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-03-06 DOI: 10.1007/s10894-025-00488-1

D. H. Zhang, X. C. Meng, G. Z. Zuo, X. Li, L. Yang, B. Cao, J. S. Hu

{"title":"Study on Corrosion Behavior of 3D-Printing W and WZrC in Static Liquid Li","authors":"D. H. Zhang, X. C. Meng, G. Z. Zuo, X. Li, L. Yang, B. Cao, J. S. Hu","doi":"10.1007/s10894-025-00488-1","DOIUrl":"10.1007/s10894-025-00488-1","url":null,"abstract":"<div>A liquid Lithium (Li) Tungsten (W)-based divertor, which combines the advantages of both W and liquid Li, is a promising solution for the divertor of future fusion reactors. The 3D printing technology, which has advantages such as the ability to process complex structures based on 3D models and high energy density suitable for the manufacturing of high-melting-point metals, will play an important role in the manufacturing of divertor components. To address the corrosion behavior of target materials in liquid Li under operational conditions, we investigated the corrosion behavior of 3D-printing W and WZrC in static liquid Li at 550 °C for 500 h. After being exposed to liquid Li, the samples exhibited mass loss, grain boundary corrosion, and pitting corrosion. The mass loss rates of W and WZrC in liquid Li were 3.3 × 10–2 and 1.76 × 10–2 g/(m2·h), respectively. The XPS and XRD results of the samples did not show significant changes before and after the test. Corrosion of liquid Li has a greater effect on the thermal conductivity of W than that of WZrC. In this study, adding ZrC to W may be an effective way to improve the liquid Li corrosion resistance of W. Reducing surface cracks may improve the resistance of 3D-printing W alloys to liquid Li corrosion.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143553783","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

Design and Analysis of Mock-up of CFETR COOL Blanket for Neutronic Experiment 中子实验用CFETR冷毯模型的设计与分析

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-27 DOI: 10.1007/s10894-025-00490-7

Qiankun Shao, Qingjun Zhu

{"title":"Design and Analysis of Mock-up of CFETR COOL Blanket for Neutronic Experiment","authors":"Qiankun Shao, Qingjun Zhu","doi":"10.1007/s10894-025-00490-7","DOIUrl":"10.1007/s10894-025-00490-7","url":null,"abstract":"<div>The purpose of this study is to design and analysis a neutronic experimental mock-up for supercritical carbon dioxide cooled Lithium-Lead (COOL) blanket of CFETR. The protype of mock-up is the equatorial outboard breeding unit (3# unit) of COOL blanket, which have the largest neutron wall loading. To verify the reliability of neutronic design of COOL blanket, the neutronic property of mock-up should be designed to be consistent with the protype. To facilitate detector layout and component installation, simplifications in radial arrangement of mock-up are necessary. The determined radial layout is arranged as Plasma Facing Component, First Wall, Gap 1, Flow Channel Insert 1 (FCI 1), Breeding Zone (BZ), Flow Channel Insert 2 (FCI 2), Gap 2 and Manifold (MF). And the dimensions of toroidal and poloidal were determined by the extent of neutrons leaking from the edge of mock-up. The determined size of the experimental mock-up is 500 mm (Toroidal)×500 mm (Poloidal)×326 mm (Radial). Ultimately, neutronic property and activation property of the mock-up is analyzed. The calculation results showed that the designed mock-up can be used to carry out neutronic experiment. This work will provide a guideline for design of next stage experiment.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143496661","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

Lithium Divertor Targets and Walls for the ASTER Liquid Stellarator Reactor, Distributed Divertor ASTER液体仿星器反应器的锂分流器靶和壁，分布式分流器

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2025-02-19 DOI: 10.1007/s10894-025-00481-8

V. Queral, A. de Castro, J. Varela, S. Cabrera, I. Fernández, D. Spong, E. Rincón

{"title":"Lithium Divertor Targets and Walls for the ASTER Liquid Stellarator Reactor, Distributed Divertor","authors":"V. Queral, A. de Castro, J. Varela, S. Cabrera, I. Fernández, D. Spong, E. Rincón","doi":"10.1007/s10894-025-00481-8","DOIUrl":"10.1007/s10894-025-00481-8","url":null,"abstract":"<div>Stellarators may have advantages for certain liquid metal options as Plasma Facing Components (PFC) for divertor targets and first walls due to the wide range of possible magnetic configurations, which additionally are free of disruptions and fast field variations. In a previous work (V. Queral et al., IEEE Trans. Plasma Sci. 52, 2024), a concept of stellarator reactor (ASTER-CP) based on swirling Li-molten salts and liquid lithium floating on the molten salt as PFC was presented. The divertor matters were not studied then and, thus, they are being studied and experimentally tested now.The ASTER-CP reactor concept, the initial liquid metal experiments and potential concepts for the ASTER-CP divertor and first wall are reported. Concerning the experiments, several small scale experiments of galinstan in a small rotating cylinder under magnetic field have been produced, including one experiment with high viscosity galinstan-mixture for increased thickness of layer. An experiment of floating lithium on the molten salt LiCl-PbCl2 gave fast volatilization/decomposition of the molten salt. Particularly for divertors, the traditional free-flow, Capillary Porous Systems and ‘divertorlets’ have been studied for application to ASTER-CP. Surface waves (hot spots), lack of enough surface fluid turbulence and excessive fluid speed are the main issues found in fast free-flow. The perhaps original concept of Distributed Divertor and Equi-power Surface is tentatively proposed and studied, taking advantage of stellarator fields and low recycling regime.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00481-8.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143446514","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: 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

引用次数: 0

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

引用次数: 0

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