K. Kasuya, S. Ozawa, S. Suzuki, K. Esato, M. Akiba
{"title":"Material Surface Ablation with ELM-like E-beam Thermal Load","authors":"K. Kasuya, S. Ozawa, S. Suzuki, K. Esato, M. Akiba","doi":"10.1109/FUSION.2007.4337886","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337886","url":null,"abstract":"One of the important issues concerning ITER wall material interactions is the diverter response against the ELMs (Edge Localized Modes). To investigate the response against the ELM-like electron beam thermal loads, various candidate materials for reactor walls were irradiated with an electron beam apparatus at JAEA Naka Laboratory (JEBIS). The ablated surface thickness and the transient surface temperature were measured and compared under the various irradiation conditions.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131037500","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Analysis on Tritium Permeation and Inventory in China DFLL-TBM for ITER","authors":"Y. Song, Q. Huang, Y. Wu","doi":"10.1109/FUSION.2007.4337909","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337909","url":null,"abstract":"The Dual-Functional Lithium-Lead Blanket Module (DFLL-TBM) system is proposed to be tested in ITER. A tritium flow model of the entire DFLL-TBM system was developed, which included the entire TBM and major components of the TBM auxiliary system. And the analysis on tritium permeation and inventory in DFLL-TBM of ITER were done based on the model by using the TAS (Tritium Analysis Software). The following items were taken into consideration, such as the tritium permeation barriers, tritium extraction both from LiPb and helium coolant, helium leakage rate from the cooling system and so on. Some factors, which may probably influence the tritium permeation, were analyzed and evaluated. The results show that the DFLL-TBM is safe from the viewpoint of the tritium according to the ITER TBM safety guard line.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"56 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123708931","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"A Second Generation Timing System for DIII-D Timing Control","authors":"T. Deterly, D. Kellman, D. Finkenthal","doi":"10.1109/FUSION.2007.4337927","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337927","url":null,"abstract":"The DIII-D Tokamak relies on a facility wide timing network to synchronize machine operations. The first generation system was designed around cascaded CAMAC delay units feeding a custom timing network encoder. This system has become increasingly difficult to maintain and repair and the needs of DIII-D experiments are beginning to exceed its capabilities. To address these issues, a new second-generation system was designed with a modular architecture in a VME form factor that facilitates the future addition of features and output channels when required, while maintaining backwards compatibility with the original system. As part of the base design, modules for event triggers, multiple programmable sequences, first generation Bi-Phase serial outputs, fiber optic outputs, and event recording are provided. Each module is implemented with a form of programmable logic, either a CPLD or FPGA, which allows for future modification if needed. The system also has the capability of complete remote management, allowing for custom timing chains on a per-experiment basis. The feature set and design of this second-generation timing system is presented.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"34 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114990480","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
D. Terry, W. Burke, A. Kanojia, P. MacGibbon, D. Johnson, R. Parker, R. Vieira, G. Wallace, W. Beck, P. Koert, J. Irby, J. Wilson, N. Greenough, D. Gwinn
{"title":"Lower Hybrid Current Drive on Alcator C-Mod: System Design, Implementation, Protection, Calibration and Performance","authors":"D. Terry, W. Burke, A. Kanojia, P. MacGibbon, D. Johnson, R. Parker, R. Vieira, G. Wallace, W. Beck, P. Koert, J. Irby, J. Wilson, N. Greenough, D. Gwinn","doi":"10.1109/FUSION.2007.4337922","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337922","url":null,"abstract":"A 4.6 GHz 3 MW lower hybrid current drive (LHCD) system has been designed and implemented on Alcator C-Mod. This RF system will allow C-Mod to access advanced tokamak regimes: high confinement, high betan, and high bootstrap fraction and extend them to quasi-steady-state conditions. The LHCD system includes twelve 250 kW klystrons. Power from each klystron is split eight ways using a complex system of waveguides to drive a 96-window coupler array. The amplitude and relative phasing of each klystron is controlled by a computer-based system using I-Q vector modulators and is monitored by I-Q detectors to control the npar spectrum applied to the plasma. Calibration is accomplished using a network analyzer in conjunction with software programs to generate two-dimensional lookup tables that allow compensation for system non-linearities. Forward and reflected powers are monitored to protect the klystrons, waveguides and coupler array from arcing. During the 2006 experimental campaign, nearly 1 MA of current was driven into Alcator C-Mod plasma using 800 kW of coupled RF power.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"46 10","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120856600","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}