2011 IEEE/NPSS 24th Symposium on Fusion Engineering最新文献_第5页

Design of an ech system for a small modular stellarator 小型模组式仿星器系统设计

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052329

H. Mora, V. Vargas, S. Tallents, L. Rivas, D. Chacon, J. Chacón, S. Fatjo, J. Jiménez, L. F. Villegas, J. Mora, J. Asenjo, J. M. Carranza, F. Cerdas, L. Barillas, J. I. Monge, J. Morera, H. Peraza, C. Rojas, G. Sanchez, M. Sandoval, J. Umaña, R. Gutierrez, G. Solano

引用次数: 2

Charting the roadmap to magnetic fusion energy 绘制磁聚变能源的路线图

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052221

G. Neilson, R. Betti, D. Gates, C. Kessel, J. Menard, S. Prager, S. Scott, M. Zarnstorff

{"title":"Charting the roadmap to magnetic fusion energy","authors":"G. Neilson, R. Betti, D. Gates, C. Kessel, J. Menard, S. Prager, S. Scott, M. Zarnstorff","doi":"10.1109/SOFE.2011.6052221","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052221","url":null,"abstract":"With the ITER era now well underway, the fusion community is considering the next major steps in magnetic fusion energy (MFE) development. It follows that there is heightened interest worldwide in understanding the roadmap to commercial MFE. In reality, there is no unique roadmap. An important differentiator among possible pathways is risk, i.e. the risks accepted in going from step to step and how risks are mitigated through R&D programs that accompany and support the progression of major nuclear devices. We consider a rollback approach, starting from a definition of what Demo (a power plant that is the last step before commercialization) must accomplish. We assess, in fusion science and technology terms, the mission and requirements for Demo, its prerequisites, and the requirements for a major nuclear devices and the accompanying programs that could precede Demo in order to satisfy its prerequisites. One option for a pre-Demo MFE device is a pilot plant, a facility that would develop and test nuclear components surrounding the plasma, prototype maintenance schemes applicable to a power plant, and demonstrate both tritium self-sufficiency and net electricity generation. An initial assessment of the pilot plant, in terms of its potential to satisfy Demo prerequisites and the associated risks, is presented.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"9 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132979873","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: 3

The ITER reactive power compensation and harmonic filtering (RPC & HF) system: Stability & performance ITER无功补偿与谐波滤波(RPC & HF)系统:稳定性与性能

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052341

A. Mankani, I. Benfatto, J. Tao, J. Goff, J. Hourtoule, J. Gascón, D. Cardoso-Rodrigues, B. Gadeau

引用次数: 30

Operation of HL-2A tokamak HL-2A托卡马克的运行

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052199

X. Duan, Y. Huang, D.Q. Liu, W. Xuan, L.Y. Chen, J. Rao, X. Song, Z. Cao, B. Li, J.Y. Cao, G. Lei, X.D. Li, Yi Liu, Q.W. Yang, L. Yao, X. Ding, J. Dong, L.W. Yan, C. Pan, Y. Liu

{"title":"Operation of HL-2A tokamak","authors":"X. Duan, Y. Huang, D.Q. Liu, W. Xuan, L.Y. Chen, J. Rao, X. Song, Z. Cao, B. Li, J.Y. Cao, G. Lei, X.D. Li, Yi Liu, Q.W. Yang, L. Yao, X. Ding, J. Dong, L.W. Yan, C. Pan, Y. Liu","doi":"10.1109/SOFE.2011.6052199","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052199","url":null,"abstract":"The operation conditions have been improved via developing new technologies and improving the hardware on HL-2A tokamak in recent years. The ECRH system has been upgraded to 3 MW/68 GHz, the supersonic molecular beam injection (SMBI) fuelling technique has been developed further, and clusters can be formed in the SMB by cooling the gas to around liquid nitrogen temperature, so that deeper penetration can be achieved. Besides, there are about 30 kinds of diagnostics developed on HL-2A to measure the plasma parameters. These diagnostic systems include magnetics, microwave reflectometry, CXRS, Thomson scattering, FIR interferometer etc. Some of them were specially designed for the physics experiments. For example, a novel design of Langmuir probes was developed to study the 3-D structure of zonal flows. With these hardware development and improvement, new experimental results have been achieved in the fields of turbulence, transport, MHD instabilities and energetic particle dynamics. In particular, the ELMy H-mode has been achieved by combining the auxiliary heating of NBI and ECRH, SMBI is beneficial for the L-H transition and the H-mode operation on HL-2A, and suitable for studying particle transport and controlling the ELMs during H-mode discharges due to its deep and local injection features and good controllability. Besides, the three dimensional spectral structures of the low frequency zonal flow and quasi-mode, which were predicted by theory and simulation, have been observed simultaneously. The beta-induced Alfvén eigenmodes (BAEs), excited by large magnetic islands (m-BAE) and by energetic electrons (e-BAE), are investigated, these phenomena are under further study.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"27 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116121772","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

Ensuring compliance and consistency in an R&D environment: The PPPL Office of Project Management 确保研发环境的遵从性和一致性:PPPL项目管理办公室

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052301

T. Dodson, T. Stevenson, T. Egebo, R. Strykowsky, S. Langish, M. Williams

引用次数: 1

The design of integrated information management system for the fusion DEMO reactor of Korea based on RDF 基于RDF的韩国DEMO聚变反应堆综合信息管理系统设计

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052273

S. Hwang, J. H. Park, J. Yoon

引用次数: 0

Performance tests of an Experimental Loop for Liquid breeder in Korea 韩国液体繁殖实验回路的性能测试

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052305

J. Yoon, S.K. Kim, Y. Jung, D.W. Lee, S. Cho

{"title":"Performance tests of an Experimental Loop for Liquid breeder in Korea","authors":"J. Yoon, S.K. Kim, Y. Jung, D.W. Lee, S. Cho","doi":"10.1109/SOFE.2011.6052305","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052305","url":null,"abstract":"Korea (KO) has developed a Liquid breeder blanket and participated in the Test Blanket Module (TBM) program within the International Thermonuclear Experimental Reactor (ITER) group with a Helium Cooled Molten Lithium (HCML) concept. Based on this concept, helium (He) and liquid lithium (Li) were used as a coolant and breeder, respectively. Additionally, ferritic martensitic (FM) steel was considered as a structural material. However, according to our strategy for developing a liquid breeder TBM and its more relevant DEMO concept, not only liquid lithium breeders, but also lead-lithium (PbLi) breeders were considered. An Experimental Loop for a Liquid breeder (ELLI) was constructed for the purpose of validating the design and fabrication of our electromagnetic (EM) pump; testing the effects of the magneto-hydro-dynamics (MHD); and investigating the compatibility of PbLi using structural materials such as ferritic martensitic steel. In the ELLI, Pb-15.7Li, where Li is 15.7 at % (called PbLi hereafter), is used as the breeding material, and the EM pump circulates it through the loop. The maximum operating pressure and temperature in the loop are 0.5 MPa and 550 °C, respectively. In this study, performance tests with the EM pump were carried out. During the three separate experiments, the EM pump was operated for 250 h with a speed of 0.16 m/s for corrosion tests. For a material of corrosion test, tubular-type specimens and cylindrical-type specimens were fabricated and installed in three test pots of the loop. After installing the specimens into the loop, the corrosion test was performed while the EM pump was operating with a 0.16 m/s flow rate at 340 °C for 250 h.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"57 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131373769","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

Development of In-vessel Vertical Coil (IVC) power supply in KSTAR KSTAR船内垂直线圈电源的研制

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052338

Jong-Kook Jin, Jae-Hoon Choi, Dong-Keun Lee, Sang-Hee Han, Y. Jeon, Yaung-Su Kim, M. Kwon, H. Ahn, G. Jang, M. Yun, D. Seong, H. Shin

引用次数: 1

The neutrons emission during the nanosecond discharge in deuterium with inhomogeneous electric field distribution

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052307

M. Lomaev, D. Sorokin, V. Tarasenko, B. Nechaev, V. N. Padalko, A. Yalovets

引用次数: 0

Design of an experimental test stand for the study of liquid lithium film stability 液体锂膜稳定性实验试验台的设计

2011 IEEE/NPSS 24th Symposium on Fusion Engineering Pub Date : 2011-06-26 DOI: 10.1109/SOFE.2011.6052314

M. Nieto-Pérez, G. Ramos

{"title":"Design of an experimental test stand for the study of liquid lithium film stability","authors":"M. Nieto-Pérez, G. Ramos","doi":"10.1109/SOFE.2011.6052314","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052314","url":null,"abstract":"The benefits of having the walls of fusion devices partially or even totally covered with lithium are widely recognized, as evidenced by the growing number of experimental devices with programs devoted to lithium wall conditioning. There are, however, many outstanding questions regarding technology aspects of lithium handling when placed in a tokamak experiment. The present work describes the preliminary design activities of a test facility devoted to the study of liquid lithium, in particular film stability when thermal gradients are present on downward-facing surfaces. The capability of studying the effect of thermodynamic compatibility between the liquid and the substarte will also be possible in this facility. Two mechanisms for film formation are being considered: condensed films formed from evaporative material, and creeping films formed by flow of metal from a liquid reservoir. Results from finite element modeling for stagnant and flowing films coupled with thermal effects are presented; these simulations will be benchmarked against experimental observations once the facility is constructed. The facility will also have the capability of studying MHD effects, since it will be attached to the TPM-1U tokamak, a small machine currently under construction. The expected TPM-1U toroidal field is expected to be on the order of 0.3 T. The coupling of the liquid lithium test stand to the small tokamak will allow the study of liquid lithium flows subjected to full toroidal fields, with no end effects as in previous experiments.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131123783","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