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The Motional Stark Effect (MSE) diagnostic is unique in its ability to measure the current profile and will be essential in ITER for detailed analysis of Advanced Tokamak (AT) and other types of discharges. However, design of a MSE diagnostic for ITER presents many unique challenges. Among these is optical analysis for the convoluted optical path, required for effective neutron shielding, that employs several reflective optics arranged to form a labyrinth. The geometry of the diagnostic has been laid out and the expected Doppler shifts and channel resolution calculated. A model of the optical train has also been developed based on the Mueller matrix formalism. Unfolding the pitch angle for this complicated geometry is not straightforward and possible methods are evaluated. The CORSICA code is used to model a variety of ITER discharges including start-up, Ipramp and reverse shear. The code also incorporates a synthetic MSE diagnostic that can be used to evaluate different viewing locations and optimize channel locations for the above discharges. Simulation of the optical emission spectrum is also underway.
The Motional Stark Effect (MSE) diagnostic will be essential for the study of advanced scenarios on ITER and its design is currently underway. In order meet the ITER MSE diagnostic design requirements, two approaches for the measurement are under consideration. The first is based on standard polarimeter techniques to measure the polarization of the emitted light, whereas the second measures the Stark splitting from which.
The advanced tokamak research program at DIII-D relies critically on the measurement of the current density profile. This was made possible by the development of a Motional Stark Effect (MSE) polarimeter that was first installed in 1992. Three major upgrades have since occurred, and improvements in our understanding of critical performance issues and calibration techniques are ongoing. In parallel with these improvements, we have drawn on our DIII-D experience to begin studies and design work for MSE on burning plasmas and ITER. This paper first reviews how Motional Stark Effect polarimetry (MSE) is used to determine the tokamak current profile. It uses the DIII-D MSE system as an example, and shows results from the latest upgrade that incorporates an array of channels from a new counter-Ip injected neutral beam. The various calibration techniques presently used are reviewed. High-leverage or unresolved issues affecting MSE performance and reliability in ITER are discussed. Next, we show a four-mirror collection optics design for the two ITER MSE views. Finally, we discuss measurements of the polarization properties of a few candidate mirrors for the ITER MSE.
The Motional Stark Effect (MSE) diagnostic on ITER determines the local plasma current density by measuring the polarization angle of light resulting from the interaction of a high energy neutral heating beam and the tokamak plasma. This light signal has to be transmitted from the edge and core of the plasma to a polarization analyzer located in the port plug. The optical system should either preserve the polarization information, or it should be possible to reliably calibrate any changes induced by the optics. This LLNL Work for Others project for the US ITER Project Office (USIPO) is focused on the design of the viewing optics for both the edge and core MSE systems. Several design constraints were considered, including: image quality, lack of polarization aberrations, ease of construction and cost of mirrors, neutron shielding, and geometric layout in the equatorial port plugs. The edge MSE optics are located in ITER equatorial port 3 and view Heating Beam 5, and the core system is located in equatorial port 1 viewing heating beam 4. The current work is an extension of previous preliminary design work completed by the ITER central team (ITER resources were not available to complete a detailed optimization of this system, and then the MSE was assigned to the US). The optimization of the optical systems at this level was done with the ZEMAX optical ray tracing code. The final LLNL designs decreased the ''blur'' in the optical system by nearly an order of magnitude, and the polarization blur was reduced by a factor of 3. The mirror sizes were reduced with an estimated cost savings of a factor of 3. The throughput of the system was greater than or equal to the previous ITER design. It was found that optical ray tracing was necessary to accurately measure the throughput. Metal mirrors, while they can introduce polarization aberrations, were used close to the plasma because of the anticipated high heat, particle, and neutron loads. These mirrors formed an intermediate image that then was relayed out of the port plug with more ideal (dielectric) mirrors. Engineering models of the optics, port plug, and neutral beam geometry were also created, using the CATIA ITER models. Two video conference calls with the USIPO provided valuable design guidelines, such as the minimum distance of the first optic from the plasma. A second focus of the project was the calibration of the system. Several different techniques are proposed, both before and during plasma operation. Fixed and rotatable polarizers would be used to characterize the system in the no-plasma case. Obtaining the full modulation spectrum from the polarization analyzer allows measurement of polarization effects and also MHD plasma phenomena. Light from neutral beam interaction with deuterium gas (no plasma) has been found useful to determine the wavelength of each spatial channel. The status of the optical design for the edge (upper) and core (lower) systems is included in the following figure. Several issues should be addressed by a follow-on study, including whether the optical labyrinth has sufficient neutron shielding and a detailed polarization characterization of actual mirrors.
ITER (the International Thermonuclear Experimental Reactor, a joint venture between Europe, Japan, Russia, USA, China, India and South Korea) will need to measure a wide range of plasma parameters in order to reach and sustain high levels of fusion power and provide input to control systems with adequate reliability and long-term stability. The conference was the first appointment of the diagnostic community after the approval of ITER, and was therefore an opportunity to review the status of ITER diagnostics with particular reference to the capabilities of the present proposed systems to meet the requirements on the measurements. Critical issues related with the measurements of fast particles, fusion products, plasma facing components and radiation effects were addressed as well as new areas of diagnostic developments related with DEMO, the next step fusion reactor that will deliver electrical power from fusion.
Magnetic Fusion Technology describes the technologies that are required for successful development of nuclear fusion power plants using strong magnetic fields. These technologies include: • magnet systems, • plasma heating systems, • control systems, • energy conversion systems, • advanced materials development, • vacuum systems, • cryogenic systems, • plasma diagnostics, • safety systems, and • power plant design studies. Magnetic Fusion Technology will be useful to students and to specialists working in energy research.
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Fusion Reactor Design Provides a detailed overview of fusion reactor design, written by an international leader in the field Nuclear fusion—generating four times as much energy from the same mass of fuel as nuclear fission—is regarded by its proponents as a viable, eco-friendly alternative to gas-fired, coal-fired, and conventional power plants. Although the physics of nuclear fusion is essentially understood, the construction of prototype reactors currently presents significant technical challenges. Fusion Reactor Design: Plasma Physics, Fuel Cycle System, Operation and Maintenance provides a systematic, reader-friendly introduction to the characteristics, components, and critical systems of fusion reactors. Focusing on the experimental Tokamak reactor, this up-to-date resource covers relevant plasma physics, necessary technology, analysis methods, and the other aspects of fusion reactors. In-depth chapters include derivations of key formulas, figures highlighting physical and structural characteristics of fusion reactors, illustrative numerical calculations, practical design examples, and more. Designed to help researchers and engineers understand and overcome the technological difficulties in making fusion power a reality, this volume: Provides in-depth knowledge on controlled thermonuclear fusion and its large-scale application in both current fusion reactors and future test reactors Covers plasma analysis, plasma equilibrium and stability, and plasma transport and confinement, and safety considerations Explains each component of fusion reactors, including divertors, superconducting coils, plasma heating and current drive systems, and vacuum vessels Discusses safety aspects of fusion reactors as well as computational approaches to safety aspects of fusion reactors Fusion Reactor Design: Plasma Physics, Fuel Cycle System, Operation and Maintenance is required reading for undergraduate and graduate students studying plasma physics and fusion reactor technology, and an important reference for nuclear physicists, nuclear reactor manufacturers, and power engineers involved in fusion reactor research and advanced technology development.