R. Bickerton, W. Booth, R. Carrera, G. Fu, G. Hallock, E. Montalvo, M. Rosenbluth, J. Van Dam
{"title":"Experimental program for the fusion ignition experiment IGNITEX","authors":"R. Bickerton, W. Booth, R. Carrera, G. Fu, G. Hallock, E. Montalvo, M. Rosenbluth, J. Van Dam","doi":"10.1109/PLASMA.1989.166280","DOIUrl":null,"url":null,"abstract":"Computer simulations, which provide part of the scientific basis for the design of IGNITEX, show that a volume-averaged temperature of 4 keV can be reached by pure ohmic heating while remaining in stable operating regimes. These predictions are consistent with experimental results of present high-field tokamaks. The experimental program is divided into three phases covering a three year operating period. The first year, after full commissioning of the magnet, vacuum, and data systems, will be used to study plasma shape, position, and profile control and to find optimum operating regimes for the experiment using hydrogen fuel. During this phase, final calibration and refinement of the diagnostics systems will take place. During the second year deuterium fuel will be used in the experiment. Studies of isotope-ratio control will be carried out. Additionally, during these phases, scaling laws for high-density, high-temperature, ohmically heated plasmas will be studied. The first D-T experiments will be performed during the last part of the second year of operation. These will provide limited neutron and alpha production and allow final refinement of neutron and alpha diagnostics. The ignited phase of the experiment will continue throughout the third year. During this time, alpha physics experiments will be conducted.<<ETX>>","PeriodicalId":165717,"journal":{"name":"IEEE 1989 International Conference on Plasma Science","volume":"66 5","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1989-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"IEEE 1989 International Conference on Plasma Science","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/PLASMA.1989.166280","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0
Abstract
Computer simulations, which provide part of the scientific basis for the design of IGNITEX, show that a volume-averaged temperature of 4 keV can be reached by pure ohmic heating while remaining in stable operating regimes. These predictions are consistent with experimental results of present high-field tokamaks. The experimental program is divided into three phases covering a three year operating period. The first year, after full commissioning of the magnet, vacuum, and data systems, will be used to study plasma shape, position, and profile control and to find optimum operating regimes for the experiment using hydrogen fuel. During this phase, final calibration and refinement of the diagnostics systems will take place. During the second year deuterium fuel will be used in the experiment. Studies of isotope-ratio control will be carried out. Additionally, during these phases, scaling laws for high-density, high-temperature, ohmically heated plasmas will be studied. The first D-T experiments will be performed during the last part of the second year of operation. These will provide limited neutron and alpha production and allow final refinement of neutron and alpha diagnostics. The ignited phase of the experiment will continue throughout the third year. During this time, alpha physics experiments will be conducted.<>