Journal of Fusion Energy最新文献_第3页

Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak 注入电流流对球形托卡马克中局部螺旋注入等离子体的 MHD 平衡重构的影响

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00460-5

J. D. Weberski, M. W. Bongard, S. J. Diem, R. J. Fonck, J. A. Goetz, M. D. Nornberg, J. A. Reusch, C. E. Schaefer, A. C. Sontag

{"title":"Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak","authors":"J. D. Weberski, M. W. Bongard, S. J. Diem, R. J. Fonck, J. A. Goetz, M. D. Nornberg, J. A. Reusch, C. E. Schaefer, A. C. Sontag","doi":"10.1007/s10894-024-00460-5","DOIUrl":"10.1007/s10894-024-00460-5","url":null,"abstract":"<div><p>Open field line currents are intrinsic to DC helicity injection plasma startup and pose a challenge for inferring the plasma equilibrium with standard reconstruction analysis. Local helicity injection (LHI) is a type of DC helicity injection which uses small, modular current sources to drive force-free current along helical field lines to produce tokamak plasmas. MHD modeling and magnetic measurements during LHI indicate the injected current streams remain coherent as helical structures on the outboard edge of a core toroidal plasma that is tokamak-like in a toroidally averaged sense. To extract core plasma equilibrium properties, external magnetic diagnostics corrected for contributions from the injected current streams are fitted by a standard Grad-Shafranov equilibrium code. An iterative approach for estimating and subtracting the stream contributions from the diagnostic signals is described and applied to a model equilibrium database to reduce systematic errors introduced by the streams. Convergence is usually attained with 2 to 4 iterations, with derived equilibrium parameters matching the prescribed axisymmetric core values to within estimated experimental uncertainties. Accurate recovery of core parameters occurs when the ratio of the net toroidal windup current from the streams to the core plasma current is less than 0.2, which is typically satisfied in most experiments.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-10-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00460-5.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142411493","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: Demonstration of Shafranov Shift by the Simplest Grad–Shafranov Equation Solution in IR-T1 Tokamak 撤稿说明：用 IR-T1 托卡马克中最简单的格拉德-沙弗诺夫方程解法证明沙弗诺夫偏移

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00468-x

A. Rahimirad, M. Emami, M. Ghoranneviss, A. Salar Elahi

引用次数: 0

Retraction Note: Multipole Moments Based Study on Determination of Toroidal Plasma Equilibrium Position and Shift 撤回说明：基于多极矩的环形等离子体平衡位置和位移测定研究

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00469-w

Ahmad Salar Elahi

引用次数: 0

Retraction Note: Nano-Scale Precipitates of Reduced Activation Steels for the Application of Nuclear Fusion Reactors 撤稿说明：用于核聚变反应堆的还原活化钢的纳米级沉淀物

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00462-3

S. Moniri, M. Ghoranneviss, M. R. Hantehzadeh, A. Salar Elahi

引用次数: 0

Neutron-Alpha Reaction Cross Section Determination by Machine Learning Approaches 通过机器学习方法确定中子-阿尔法反应截面

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00461-4

Naima Amrani, Cafer Mert Yeşilkanat, Serkan Akkoyun

引用次数: 0

Retraction Note: Effects of Hot Limiter Biasing on Tokamak Runaway Discharges 撤回说明：热限制器偏置对托卡马克失控放电的影响

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00464-1

A. Salar Elahi, M. Ghoranneviss, M. R. Ghanbari

引用次数: 0

Retraction Note: Feedback System Design for Plasma Horizontal Position Control in IR-T1 Tokamak 撤回说明：IR-T1 托卡马克中等离子体水平位置控制的反馈系统设计

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00463-2

A. Naghidokht, R. Khodabakhsh, M. Ghoranneviss, A. Salar Elahi

引用次数: 0

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 1.9 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

引用次数: 0

Retraction Note: Comparison between Discrete Magnetic Coils and Multipole Coils for Measurement of Plasma Displacement in IR-T1 Tokamak 撤回说明：用于测量 IR-T1 托卡马克中等离子体位移的分立磁线圈与多极线圈之间的比较

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-08-29 DOI: 10.1007/s10894-024-00459-y

Ahmad Rahimirad, M. Emami, M. Ghoranneviss, A. Salar Elahi

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":"10.1007/s10894-024-00455-2","url":null,"abstract":"<div><p>The self-sufficient supply of tritium in the deuterium-tritium nuclear fusion demonstration reactor (DEMO) is a fundamental design requirement. But, it is hindered by depletion of tritium breeding materials resulting in reduction of tritium breeding ratio (TBR) less than the initial design value especially in the solid-state tritium breeding blanket (TBB) of the DEMO. Unlike the liquid tritium breeding blanket of DEMO, compensation measures of the depleted breeding material in the solid-state TBB will be its substitution depending on the reduction rate of TBR. To estimate the replacement period of the solid-state TBB, it is required to estimate the reduction rate of TBR according to the operation conditions of the DEMO and the physical configuration of a solid-state TBB. In this study, the representative simulation codes, MCNP and FISPACT-II, are used for assessment of the reduction rate of TBR with the benchmarking model which is modified from the one poloidal segment of the TBB in the Korean-DEMO. After 3 full power-year operations with the neutron irradiation with the benchmarking model, the TBR simulated by MCNP is reduced to 96.84% of the initially calculated TBR, but the TBR calculated by FISPACT-II is reduced to 90.57% of the initially calculated TBR.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00455-2.pdf","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":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0