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Languages : en
Pages : 9
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The DIII-D program focuses on developing fusion physics in an integrated program of tokamak concept improvement. The intent is both to support the present ITER physics R and D and to develop more efficient concepts for the later phases of ITER and eventual power plants. Progress in this effort can be best summarized by recent results for a diverted deuterium discharge with negative central shear which reached a performance level of Q{sub DT} = 0.32. The ongoing development of the tools needed to carry out this program of understanding and optimization continues to be crucial to its success. Control of the plasma cross-sectional shape and the internal distributions of plasma current, density, and rotation has been essential to optimizing plasma performance. Advanced divertor concepts provide edge power and particle control for future devices such as ITER and provide techniques to help manage the edge power and particle flows for advanced tokamak concepts. New divertor diagnostics and improved modeling are developing excellent divertor understanding. Many of the plasma physics issues being posed by ITER are being addressed. Scrapeoff layer power flow is being characterized to provide an accurate basis for the design of reactor devices. Ongoing studies of the density limit focus on identifying ways in which ITER can achieve the required densities in excess of the Greenwald limit. Better understanding of disruptions is crucial to the design of future reactors.
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Languages : en
Pages : 9
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Book Description
The DIII-D program focuses on developing fusion physics in an integrated program of tokamak concept improvement. The intent is both to support the present ITER physics R and D and to develop more efficient concepts for the later phases of ITER and eventual power plants. Progress in this effort can be best summarized by recent results for a diverted deuterium discharge with negative central shear which reached a performance level of Q{sub DT} = 0.32. The ongoing development of the tools needed to carry out this program of understanding and optimization continues to be crucial to its success. Control of the plasma cross-sectional shape and the internal distributions of plasma current, density, and rotation has been essential to optimizing plasma performance. Advanced divertor concepts provide edge power and particle control for future devices such as ITER and provide techniques to help manage the edge power and particle flows for advanced tokamak concepts. New divertor diagnostics and improved modeling are developing excellent divertor understanding. Many of the plasma physics issues being posed by ITER are being addressed. Scrapeoff layer power flow is being characterized to provide an accurate basis for the design of reactor devices. Ongoing studies of the density limit focus on identifying ways in which ITER can achieve the required densities in excess of the Greenwald limit. Better understanding of disruptions is crucial to the design of future reactors.
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Languages : en
Pages : 20
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Languages : en
Pages : 36
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Languages : en
Pages : 196
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This report discusses the following topics on Doublet-3 research operations: DIII-D Program Overview; Boundary Plasma Research Program/Scientific Progress; Radio Frequency Heating and Current Drive; Core Physics; DIII-D Operations; Program Development; Support Services; ITER Contributions; Burning Plasma Experiment Contributions; and Collaborative Efforts.
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Languages : en
Pages : 18
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This document summarizes Lawrence Livermore National Laboratory's (LLNL) plan for fusion research on the DIII-D Tokamak, located at General Atomics (GA) in San Diego, California, in the time period FY04-FY08. This document is a companion document to the DIII-D Five-Year Program Plan; which hereafter will be referred to as the ''D3DPP''. The LLNL Collaboration on DIII-D is a task-driven program in which we bring to bear the full range of expertise needed to complete specific goals of plasma science research on the DIII-D facility. This document specifies our plasma performance and physics understanding goals and gives detailed plans to achieve those goals in terms of experimental leadership, code development and analysis, and diagnostic development. Our program is designed to be consistent with the long-term mission of the DIII-D program as documented in the D3DPP. The overall DIII-D Program mission is ''to establish the scientific basis for the optimization of the tokamak approach to fusion energy production''. LLNL Magnetic Fusion Energy (MFE) supports this mission, and we contribute to two areas of the DIII-D program: divertor physics and advanced tokamak (AT) physics. We lead or contribute to the whole cycle of research: experimental planning, diagnostic development, execution of experiments, and detailed analysis. We plan to continue this style in the next five years. DIII-D has identified three major research themes: AT physics, confinement physics, and mass transport. The LLNL program is part of the AT theme: measurement of the plasma current profile, and the mass transport theme: measurement and modeling of plasma flow. In the AT area, we have focused on the measurement and modeling of the current profile in Advanced Tokamak plasmas. The current profile, and it's effect on MHD stability of the high-[beta] ''AT'' plasma are at the heart of the DIII-D program. LLNL has played a key role in the development of the Motional Stark Effect (MSE) diagnostic. Starting with a single channel, the system has grown to 40 channels with three separate systems. We have continually developed new calibration techniques, with a goal of accuracy in the magnetic field pitch angle measurements of ≈0.1 degree. Measurements of the radial electric field E{sub r} have also been achieved. In the next five year period, GA plans on rotating one of the neutral beams so that it injects opposite to the sense of the plasma current (counter-injection). This enables two orthogonal MSE views of the neutral beam so that J(r) and E{sub r} can be obtained directly. In addition, the new views can be optimized so that increased spatial resolution will be obtained. Our plan is to install these new systems when the neutral beam is reoriented, and continue to provide high-resolution, ''state of the art'' current profile measurements for the DIII-D AT program. In the divertor physics area, our goal is the development of a model of the scrapeoff layer (SOL) and divertor plasmas which is benchmarked with data. We have identified the need for measurements of SOL flow and ion temperature. Working with GA, we are proposing a new edge Charge Exchange Recombination (CER) diagnostic. The understanding of SOL flow is important for understanding the tritium inventory problem in ITER. In addition, using plasma flow to ''entrain'' impurities in the divertor region (enabling a low density radiative divertor) is the current AT divertor heat flux control scenario. We are also augmenting our edge modeling capabilities with a coupled UEDGE (fluid code) with the BOUT (edge turbulence) code. Further work, funded through LLNL theory, is planned to develop a kinetic treatment of the edge. All of these efforts contribute to the understanding of the edge pedestal in the tokamak, an important AT and ITER topic. A secondary goal is the understanding of Edge Localized Modes (ELMs), which are also important in the ITER design, as the repetitive bursts of heat flux can cause increased erosion and damage to the divertor plates. The modeling effort, particularly the kinetic treatment of the pedestal region described above, is aimed at an understanding of the pedestal plasma. We plan to add fast data acquisition to several of the DIII-D edge and SOL diagnostics, e.g. the filterscopes, and imaging spectroscopic cameras, so that we can study the fast time evolution of ELMs.
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Languages : en
Pages : 400
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During the ten-year DIII-D tokamak operating period of 1989 through 1998, major scientific advances and discoveries were made and facility upgrades and improvements were implemented. Each year, annual reports as well as journal and international conference proceedings document the year-by-year advances (summarized in Section 7). This final contract report, provides a summary of these historical accomplishments. Section 2 encapsulates the 1998 status of DIII-D Fusion Science research. Section 3 summarizes the DIII-D facility operations. Section 4 describes the major upgrades to the DIII-D facility during this period. During the ten-year period, DIII-D has grown from predominantly a General Atomics program to a national center for fusion science with participants from over 50 collaborating institutions and 300 users who spend more than one week annually at DIII-D to carry out experiments or data analysis. In varying degrees, these collaborators participate in formulating the research program directions. The major collaborating institution programs are described in Section 6.
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Languages : en
Pages : 54
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The DIII-D research program is a science program aimed at an energy goal as stated in the mission statement: ''To establish the scientific basis for the optimization of the tokamak approach to fusion energy production.'' The focus is on advanced tokamak (AT) research with a goal aimed at discovering the ultimate potential of the tokamak. The research program is a multi-institutional, collaborative effort involving 60 institutions and about 300 researchers. The DIII-D tokamak has considerable plasma shape flexibility, plasma feedback control tools and algorithms and a full set of mature diagnostics for detailed studies of plasma stability, turbulence and transport, heating and current drive with neutral beams and electron cyclotron power available, and boundary and divertor physics. Along with these broad topical science areas (TSAs) of research several more focused areas of research, called thrusts, are chosen each year. This year the thrusts were on a high bootstrap fraction (fBS) AT scenario, stabilization of resistive wall modes (RWMs), internal transport barrier (ITB) control, understanding and control of the edge pedestal, and stabilization of neoclassical tearing modes (NTMs).
Author: United States. Department of Energy
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Category : Nuclear fusion
Languages : en
Pages :
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Category :
Languages : en
Pages : 75
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The DIII-D research program funded by the U.S. Department of Energy (DOE) is aimed at developing the knowledge base for an economically and environmentally attractive energy source for the nation and the world. The DIII-D program mission is to advance fusion energy science understanding and predictive capability and improve the tokamak concept. The DIII-D scientific objectives are: (1) Advance understanding of fusion plasma physics and contribute to the physics base of ITER through extensive experiment and theory iteration in the following areas of fusion science - Magnetohydrodynamic (MHD) stability - Plasma turbulence and transport - Wave-particle interactions - Boundary physics plasma neutral interaction (2) Utilize scientific understanding in an integrated manner to show the tokamak potential to be - More compact by increasing plasma stability and confinement to increase the fusion power density ([Beta][tau]) - Steady-state through disruption control, handling of divertor heat and particle loads and current drive (3) Acquire understanding and experience with environmentally attractive low activation material in an operating tokamak. This report contains the research conducted over the past year in search of these scientific objectives.
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Languages : en
Pages : 4
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The DIII-D National Team consists of about 120 operating staff and 100 research scientists drawn from 9 U.S. National Laboratories, 19 foreign laboratories, 16 universities, and 5 industrial partnerships. This multi-institution collaboration carries out the integrated DIII-D program mission which is to establish the scientific basis for the optimization of the tokamak approach to fusion energy production. Presently, about two-thirds of the research physics staff are from the national and international collaborating institutions.
