发布求助
文献互助 智能选刊 最新文献

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering最新文献

筛选
英文 中文
110 GHz ECH on DIII-D: system overview and initial operation DIII-D上的110 GHz ECH:系统概述和初始操作
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218701
W. Cary, J.C. Allen, R. Callis, J. Doane, T. E. Harris, C. Moeller, A. Nerem, R. Prater, D. Remsen
{"title":"110 GHz ECH on DIII-D: system overview and initial operation","authors":"W. Cary, J.C. Allen, R. Callis, J. Doane, T. E. Harris, C. Moeller, A. Nerem, R. Prater, D. Remsen","doi":"10.1109/FUSION.1991.218701","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218701","url":null,"abstract":"A new high-power electron cyclotron heating (ECH) system has been introduced on DIII-D. This system is designed to operate at 110 GHz with a total output power of 2 MW. The system consists of four Varian VGT-8011 gyrotrons, (output power of 500 kW), and their associated support equipment. All components have been designed for up to a 10-s pulse duration. The 110-GHz system is intended to further progress in RF current drive experiments on DIII-D when used in conjunction with the existing 60-GHz ECH (1.6-MW) and 30-60-MHz ICH (2-MW) systems. H-mode physics, plasma stabilization experiments, and transport studies are also to be conducted at 110 GHz. The system design philosophy was based on experience gained from the existing 60-GHz ECH system. The consequences of these design decisions are addressed, as is the performance of various 110-GHz components.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128285272","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: 6
Design of the advanced divertor pump cryogenic system for DIII-D DIII-D先进导流泵低温系统设计
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218650
K. Schaubel, C. Baxi, G. Campbell, A. M. Gootgeld, A. Langhorn, G. J. Laughon, J. P. Smith, P. M. Anderson, M. M. Menon
{"title":"Design of the advanced divertor pump cryogenic system for DIII-D","authors":"K. Schaubel, C. Baxi, G. Campbell, A. M. Gootgeld, A. Langhorn, G. J. Laughon, J. P. Smith, P. M. Anderson, M. M. Menon","doi":"10.1109/FUSION.1991.218650","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218650","url":null,"abstract":"The design of the cryogenic system for the DIII-D advanced divertor cryocondensation pump is presented. The advanced divertor incorporates a baffle chamber and bias ring located near the bottom of the DIII-D vacuum vessel. A 50000-l/s cryocondensation pump will be installed underneath the baffle for plasma particle exhaust. The pump consists of a liquid-helium-cooled tube operating at 4.3 K and a liquid-nitrogen-cooled radiation shield. Liquid helium is fed by forced flow through the cryopump. Compressed helium gas flowing through the high-pressure side of a heat exchanger is regeneratively cooled by the two-phase helium leaving the pump. The cooled high-pressure gaseous helium is then liquefied by a Joule-Thomson expansion valve. The liquid is returned to a storage dewar. The liquid nitrogen for the radiation shield is supplied by forced flow from a bulk storage system. Control of the cryogenic system is accomplished by a programmable logic controller.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"253 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133838414","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: 4
The use of a VAX cluster for the DIII-D data acquisition system 使用VAX集群进行DIII-D数据采集系统
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218713
B. McHarg
{"title":"The use of a VAX cluster for the DIII-D data acquisition system","authors":"B. McHarg","doi":"10.1109/FUSION.1991.218713","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218713","url":null,"abstract":"The author describes the configuration of the DIII-D mixed interconnect VAX cluster and how it has improved the efficiency of data collection, system management, and personnel efficiency. The use of a VAX console system for central console management is also described. To improve the efficiency of the overall data acquisition system, a mixed interconnect VAX cluster has been formed consisting of 16 VAX computers. In the cluster, the software protocol for passing data around the cluster is much more efficient than using DECnet. The cluster has also greatly simplified the procedure of backing up disks. Another big improvement is the use of a VAX console system which ties all the console ports of the computers into one central computer system, which then manages the entire cluster.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"100 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130404304","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
Optimization of thermal design for nitrogen shield of JET cryopump JET低温泵氮屏蔽热设计优化
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218651
C. Baxi, W. Obert
{"title":"Optimization of thermal design for nitrogen shield of JET cryopump","authors":"C. Baxi, W. Obert","doi":"10.1109/FUSION.1991.218651","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218651","url":null,"abstract":"Thermal analysis of the nitrogen shield of the JET (Joint European Torus) cryopump was done using a finite element computer program. In this analysis, a parallel flow arrangement and two series flow arrangements were compared for cooldown from 300 to about 80 K. In order to simplify the analysis, coolant was assumed to be a N/sub 2/ gas at an inlet temperature of 80 K. It is shown that all three flow arrangements have similar time for cooling down the shield from 300 to 80 K. This means that the heat exchange effect or radial conduction from the warm part of the shield to the cold part of the shield for series flow arrangements is not dominant. Due to small conduction effects, it will be feasible to modify the design to a more stable series flow arrangement. This flow arrangement will also have minimum cooling time. The inner stainless steel shield has small thermal conductivity and, hence, this part of the shield lags in cooling behind the rest of the shield. This could be remedied by adding about a 1-mm layer of copper in poloidal stripes to the stainless steel fin.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"60 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127129863","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
DIII-D radiation shielding procedures and experiences DIII-D辐射屏蔽程序和经验
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218845
P. Taylor
{"title":"DIII-D radiation shielding procedures and experiences","authors":"P. Taylor","doi":"10.1109/FUSION.1991.218845","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218845","url":null,"abstract":"The DIII-D tokamak operates with a neutron radiation shield to allow enhanced plasma operations with increased neutron production while minimizing the site boundary dose level. Neutron rates as high as 4*10/sup 15/ neutron/s and total neutron production as high as 4*10/sup 15/ neutrons per shot are obtained while maintaining the site dose below the DOE (Department of Energy) administrative level of 20 mrem per year. The radiation shielding has increased by a factor of 300 over the preshield value and is in agreement with the design calculation. The maximum site neutron dose since installation of the shield has been less than 0.03 mrem for a shot and less than 0.4 mrem for a day. The site neutron and gamma dose are monitored continuously during operations by a PC-based computer system that provides the means of measuring the low dose levels that occur during a shot by including postshot background subtraction. The neutron and gamma dose are measured and archived by shot, hour, and day in a database. Activation of the machine after a run day and during vessel entries is monitored, and the activated nuclides have been determined.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"35 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122346392","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
Software upgrade for the DIII-D neutral beam control systems DIII-D中性波束控制系统的软件升级
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218719
J. Cummings, P. Thurgood
{"title":"Software upgrade for the DIII-D neutral beam control systems","authors":"J. Cummings, P. Thurgood","doi":"10.1109/FUSION.1991.218719","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218719","url":null,"abstract":"The Neural Beam Software Upgrade project was launched in early 1990. The major goals were to upgrade the MAX IV operating system to the latest version (K.1), use standard MODCOMP software (as much as possible), and to develop a very user-friendly, versatile system. Accomplishing these goals required new software to be developed and modifications to existing applications software to make it compatible with the latest operating system. The custom operating system modules to handle the message service and interrupt handling were replaced by the standard MODCOMP intertask communication (ITC) and interrupt routines that are part of the MAX IV operating system. The message service provides the mechanism for doing shot task sequencing. The interrupt routines are used to connect external interrupts to the system. The new software developed consists of a task dispatcher, a screen manager, and interrupt tasks. The existing applications software had to be modified to be compatible with the MODCOMP ITC services and consists of the Modcomp Infinity Data Base Manager, a multiuser system, and menu-driven operator system interface routines using the Infinity Data Base Manager.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"43 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121455604","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
30-60 MHz FWCD system on DIII-D: power division, phase control and tuning for a four-event antenna array DIII-D上的30-60 MHz FWCD系统:四事件天线阵列的功率划分、相位控制和调谐
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-11-01 DOI: 10.1109/FUSION.1991.218938
R. Pinsker, M. Mayberry, C. Petty, W. Cary, J. Pusl, D. Remsen, F. Baity, R. Goulding, D.J. Hofmann
{"title":"30-60 MHz FWCD system on DIII-D: power division, phase control and tuning for a four-event antenna array","authors":"R. Pinsker, M. Mayberry, C. Petty, W. Cary, J. Pusl, D. Remsen, F. Baity, R. Goulding, D.J. Hofmann","doi":"10.1109/FUSION.1991.218938","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218938","url":null,"abstract":"The 2-MW fast wave current drive system on DIII-D is intended to provide near-term demonstration of up to 0.3 MA of current driven by the fast wave. The system used to drive the four-element phased antenna array which produces the required directional spectrum is presented. This system must be able to cope with strong coupling between antenna elements and the time-varying plasma load seen by the antennas. Computer modeling shows that this system should be able to maintain a directional spectrum at full power under most anticipated load conditions.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"9 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126870923","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: 6
Small inertial fusion energy (IFE) demonstration reactors 小型惯性聚变能(IFE)示范反应堆
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-10-03 DOI: 10.1109/FUSION.1991.218911
W. Hogan
{"title":"Small inertial fusion energy (IFE) demonstration reactors","authors":"W. Hogan","doi":"10.1109/FUSION.1991.218911","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218911","url":null,"abstract":"ICF (inertial confinement fusion) target design studies done for the Nova Upgrade have identified conditions under which the target ignition 'cliff' is shifted to much lower drive energy, albeit with the penalty that the gain achieved at a given drive energy is also smaller. These targets would repeatably produce the output and spectra of higher gain targets at low yield. They should thus allow building much smaller R&D reactors with full thermonuclear effects. Demonstration reactors at the 1 to 100 MW/sub e/ level appear to be feasible with driver energies of 0.5 to 2.0 MJ/pulse. These smaller, less expensive test and demonstration facilities should result in a lower IFE development cost. If the US government builds a driver and target factory, it is also conceivable that commercial organizations could build their own scaled concepts of IFE reactors using the beams and targets supplied by the government's facilities.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"23 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129124788","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: 5
Final optics for laser-driven inertial fusion reactors 激光驱动惯性聚变反应堆的最终光学
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-10-02 DOI: 10.1109/FUSION.1991.218705
J. Woodworth, L. Chase, M. Guinan, W. Krupke, W.R. Sooy
{"title":"Final optics for laser-driven inertial fusion reactors","authors":"J. Woodworth, L. Chase, M. Guinan, W. Krupke, W.R. Sooy","doi":"10.1109/FUSION.1991.218705","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218705","url":null,"abstract":"A promising concept for the final optics of a baseline laser-driven ICF (inertial confinement fusion) reactor is described. It addresses the problem of long-term survival of the final optics with respect to neutron damage. The use of refractive optics is considered. A baseline design consists of two wedges of fused silica, which put a dogleg into the beam and thus remove optics further upstream from direct sight of the reactor. If the closest optic were located 40 m from the center of a 3-GWt reactor, it would be subject to an average 14-MeV neutron flux of approximately=5*10/sup 12/ n/s-cm/sup 2/ with a peak flux of approximately=6*10/sup 18/ n/s-cm/sup 2/. A major question to be answered is: What duration of reactor operation can this optic withstand? To answer this question, the literature bearing on radiation-induced optical damage in fused silica was reviewed to assess its implications for reactor operation with the baseline final optics scheme. It appears possible to continuously anneal the neutron damage in the silica by keeping the wedge at a modestly elevated temperature. The literature review indicates that the proposed final optic material-fused silica-is structurally resistant to radiation damage and that if operated at a temperature of about 300 degrees C will remain optically clear.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"225 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127199262","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
Verification test for helium panel of cryopump for DIII-D advanced divertor DIII-D高级导流器低温泵氦板验证试验
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-10-01 DOI: 10.1109/FUSION.1991.218649
C. Baxi, G.J. Loughon, A. Langhorn, K. Schaubel, J.P. Smith, A. M. Gootgeld, G. Campbell, M. Menon
{"title":"Verification test for helium panel of cryopump for DIII-D advanced divertor","authors":"C. Baxi, G.J. Loughon, A. Langhorn, K. Schaubel, J.P. Smith, A. M. Gootgeld, G. Campbell, M. Menon","doi":"10.1109/FUSION.1991.218649","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218649","url":null,"abstract":"It is planned to install a cryogenic pump, in the lower divertor portion of the DIII-D tokamak with a pumping speed of 50000 l/s and an exhaust of 2670 Pa-l/s (20 torr-l/s). A coaxial counterflow configuration has been chosen for the helium panel of this cryogenic pump. The cool-down rates and fluid stability of this configuration are evaluated. A prototypic test was performed to increase confidence in the design. That the helium panel cooldown rate agreed quite well with analytical prediction and was within acceptable limits. The design flow rate proved stable and two-phase pressure drop can be predicted quite accurately. Results confirm that a cooldown of the helium panel from 300 K to liquid helium temperature can be achieved in the few minutes available between plasma shots. Helium flow results indicate that, at the design flow rate of 5 g/s, flow will be stable for heat loads up to 54 W. The expected heat load on the helium panel during operation is about 10 W.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"30 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124023639","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
首页 上一页 下一页 尾页
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整，为了账户安全，请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们：info@booksci.cn Book学术提供免费学术资源搜索服务，方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号：481959085
Book学术官方微信