2007 IEEE 22nd Symposium on Fusion Engineering最新文献

Intensity Distribution of D-3He Fusion Reaction Rate in an IEC Device D-3He在IEC器件中聚变反应速率的强度分布

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337870

T. Fujimoto, T. Oishi, H. Zen, K. Masuda, K. Yoshikawa

引用次数: 4

Performance Analysis of a Hybrid IGCTs-Mechanical Dc Circuit Breaker for Quench Protection of Superconducting Magnets 超导磁体猝灭保护用igcts -机械式混合式直流断路器的性能分析

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337931

R. Piovan, E. Gaio, L. Novello

引用次数: 14

Engineered Surfaces for the Lithium Tokamak Experiment (LTX) 锂托卡马克实验(LTX)工程表面

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337875

J. S. O'Dell, R. Majeski, J. Timberlake

{"title":"Engineered Surfaces for the Lithium Tokamak Experiment (LTX)","authors":"J. S. O'Dell, R. Majeski, J. Timberlake","doi":"10.1109/FUSION.2007.4337875","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337875","url":null,"abstract":"Reactor studies have identified liquid lithium walls as a promising solution to magnetic fusion energy (MFE) first wall problems. The difficulty of translating thick (0.1-1 mm) liquid metals into a full-wall solution has led to the pursuit of the \"thin-film\" approach (100-10,000 nm) for near-term applications such as the Lithium Tokamak experiment (LTX). However, thin lithium films can become saturated with hydrogen and form LiH, which is not attractive as a plasma facing component. A \"thick\" lithium film approach would enable hundreds of discharges without the formation of LiH. During this investigation, an engineered surface comprised of a porous refractory metal in which lithium is embedded is being developed to enable the evaluation of a thick lithium film approach for plasma facing components (PFCs). Innovative vacuum plasma spray forming techniques are being used to produce the porous refractory metal surface. Initial resistive heating tests have demonstrated the excellent wetting characteristics of the plasma spray formed porous deposits with liquid lithium. This paper will discuss the development of the engineered surfaces including resistive heating experiments of the porous surfaces with liquid lithium and the status of the effort to coat the full size LTX shell.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"28 19 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":"127260711","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}

引用次数: 0

Computational Analysis of the Magnetic Intervention Concept for First Wall Protection from Energetic Ions in a Direct Drive Laser Fusion Chamber 直接驱动激光聚变室高能离子第一壁保护磁干预概念的计算分析

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337893

D. Rose, D. Welch, T. Genoni, R. Clark, A. E. Robson, J. Giuliani, J. Sethian

引用次数: 0

The In-Vessel 3D Inspection System For ITER ITER的船内三维检测系统

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337921

C. Neri, L. Bartolini, A. Coletti, M. F. de Collibus, G. Fornetti, S. Lupini, F. Pollastrone, M. Riva, L. Semeraro

引用次数: 3

Basic research of the solid electrolyte as a sensor for the purity control of the liquid metal LiPb 固体电解质作为液态金属LiPb纯度控制传感器的基础研究

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337868

I. Atsunori, Y. Yoshihiko, Y. Yasushi, K. Satoshi

引用次数: 0

Dose Measurement and Analysis of EAST in the 2007 Spring Experiment 2007年春季实验中EAST的剂量测量与分析

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337894

G. Song, G. Li, Z. Tang, M. Cheng, J. Jing, Q. Huang, Y. Wu

{"title":"Dose Measurement and Analysis of EAST in the 2007 Spring Experiment","authors":"G. Song, G. Li, Z. Tang, M. Cheng, J. Jing, Q. Huang, Y. Wu","doi":"10.1109/FUSION.2007.4337894","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337894","url":null,"abstract":"The radiation generated by EAST in the 2007 spring experiment was mainly photons and a few photoneutrons. In order to measure and analyze the radiation field of the EAST device, 6LiF(Mg,Cu,P) and 7LiF(Mg,Cu,P) thermoluminescence detectors (TLDs) were applied to determine the photon and neutron dose equivalent distributions in the EAST hall, the central control room and the surrounding environment. The measurement results showed that the accumulated doses equivalent and the estimated average dose rates equivalent in the tokamak hall were very high during the whole experiment period and the discharge period, respectively. So any personnel accessing into the hall or staying in the hall during the plasma discharge periods should be prohibited automatically by the safety interlock. The doses equivalent in the central control room and the surrounding environment during the experiment period were just a little higher than the background level, and the dose influence on the staff and the ambient inhabitants was slight except the entrance areas of the EAST hall, where very high photon and neutron doses equivalent appeared. Effective measures should be carried out in the entrance areas as soon as possible to reduce the radiation levels during discharge periods.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"19 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":"127020475","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}

引用次数: 2

Comparison of the Au and Ta Foil Parameters from laser Calibration of Imaging Bolometer Foils 激光标定成像测热计箔中Au和Ta箔参数的比较

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337918

H. Parchamy, B. Peterson, H. Hayashi, S. Konoshima, N. Ashikawa

{"title":"Comparison of the Au and Ta Foil Parameters from laser Calibration of Imaging Bolometer Foils","authors":"H. Parchamy, B. Peterson, H. Hayashi, S. Konoshima, N. Ashikawa","doi":"10.1109/FUSION.2007.4337918","DOIUrl":"https://doi.org/10.1109/FUSION.2007.4337918","url":null,"abstract":"The calibration technique of the imaging bolometer foil gives confidence in the measured values of the plasma radiation power. In this paper we improve the accuracy of the calibration of the imaging bolometer foil by using an IR camera (FLIR/SC500) (60 Hz, 320 x 240 pixels, 7.5-13 mum) in a calibration laboratory (low noise environment) with a close-up lens, which provides a spatial resolution of ~0.09 mm which is ~7 times better than the previous in situ calibration using a different IR camera (Indigo/Omega) (30 Hz, 160 x 120 pixels, 7.5-13.5 mum). In addition the foil material is changed for the development of the imaging bolometer. Tantalum (Ta) is offered for improved sensitivity, foil strength, and lower neutron cross-section compared to the previously used gold foil of the imaging bolometer for the JT-60U tokamak. In this paper we report the local foil properties (the thermal conductivity (constant), and the thickness) of a single graphite-coated gold foil (a nominal thickness of 2.5 mum) for LHD compared with those of a single graphite-coated tantalum foil (a nominal thickness of 5 mum) for JT-60U by calibration with a He-Ne laser.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"9 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":"124204849","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}

引用次数: 1

Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX) 导流器冲蚀与蒸汽屏蔽实验(DEVeX)综述与现状

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337925

T. Gray, M.J. Williams, D. Ruzic

引用次数: 5

Limiter Thermography in ADITYA Tokamak ADITYA托卡马克的限制热成像

2007 IEEE 22nd Symposium on Fusion Engineering Pub Date : 2007-06-17 DOI: 10.1109/FUSION.2007.4337923

S. Bhatt, L. Lachhvani, J. Govindarajan, D. C. Reddy, S. Pandya, K. Jadeja

引用次数: 1