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Your search keyword '"toroidal field magnet"' showing total 11 results
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11 results on '"toroidal field magnet"'

1. JT-60SA TF magnet assembly.

Author

Davis, Sam, Hajnal, Nandor, Hayakawa, Atsuro, Mayri, Christophe, Masaki, Kei, Okano, Fuminori, Shibama, Yusuke, Tomarchio, Valerio, Tsuchiya, Katsuhiko, and Yagyu, Junnichi

Subjects
*MAGNETIC fields, *SUPERCONDUCTING magnets
Abstract

JT-60SA will be the world's largest superconducting tokamak when it is assembled in 2020 in Naka, Japan (R = 3 m, a = 1.2 m). It is being constructed jointly by institutions in the EU and Japan under the Broader Approach agreement. The assembly of its 400-tonne toroidal field (TF) magnet, designed for an on-axis field of 2.25 T, was completed in July 2018. Consideration of its assembly throughout the design process, with associated consultation and testing, allowed high positional accuracy and hence respect for magnetic field tolerances to be achieved. [ABSTRACT FROM AUTHOR]

Published
2019
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2. Superconducting Magnet

Author

Du, Shijun, Wu, Weiyue, Song, Yuntao, Liu, Xufeng, Zheng, Jinxing, Ling, Frederick F., Editor-in-chief, Winer, Ward O., Series editor, Bergles, Arthur E., Series editor, Klutke, Georgia A., Series editor, Wang, Kuo K., Series editor, Finnie, Iain, Series editor, Welty, J. R., Series editor, Bryant, Michael D., Series editor, Yang, Henry T., Series editor, Mow, Van C., Series editor, Leckie, Frederick A., Series editor, Gross, Dietmar, Series editor, Song, Yuntao, Wu, Weiyue, and Du, Shijun

Published
2014
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3. Optimization of the ITER Precompression Ring Test Rig Flange.

Author

Reccia, Luigi, Semeraro, Luigi, Richiusa, Maria Lorena, Bonito-Oliva, Alessandro, Mitchell, Neil, and Boyer, Christelle

Subjects
*MAGNETIC fields, *HYDRAULIC cylinders, *ELECTROMAGNETIC theory, *SIMULATION methods & models, *FIELD theory (Physics)
Abstract

The precompression ring (PCR) is an important element of the ITER magnetic system since it improves the force distribution among the toroidal field magnets during plasma operation. An experimental campaign has been planned at the ITER organization to characterize themechanical behavior of the ring in a test rig able to simulate the ITER assembly conditions. In particular, the testing machine aims at simulating the effect of the preload by means of a system of hydraulic cylinders capable to deliver 36 000 tons of radial pushing force. A steel "cushion" flange acts as interface between the cylinders and the ring distributing the pressure on the surface and preventing the PCR from local breakage. In this paper, the shape optimization of such flange is addressed, identifying the optimal geometry basing on the contact stress on the inner surface of the PCR. The study shows how the stress peaks can be avoided by obtaining a reasonably homogeneous distribution limiting the risks of peak stresses that might compromise the integrity of the component. The results of this study can also be used as a basis of future studies aiming at optimizing the ITER flange design and the behavior of the PCR in operative conditions. [ABSTRACT FROM AUTHOR]

Published
2018
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5. THE 4K MECHANICAL PROPERTIES OF MODIFIED SS316LN FOR JACKET MATERIALS IN SUPERCONDUCTING FUSION MAGNETS.

Author

Ji Hyun Kim and Jun Feng

Subjects
*STAINLESS steel, *MECHANICAL properties of metals, *SUPERCONDUCTING magnets, *HEAT treatment of steel, *COLD working of steel
Abstract

Modified stainless steel 316LN (SS316LN) is designed as ITER TF jacket materials for the application at 4K. The mechanical properties of modified SS316LN have been measured at both room temperature and 4K in order to evaluate its suitability as the candidate materials for ITER TF jacket. The effects of cold work and aging heat treatments have also been studied using two different modified SS316LN steels. It is found that both base and weld materials of the modified SS316LN after cold work and aging satisfy the designed requirement of mechanical properties for ITER TF jacket. [ABSTRACT FROM AUTHOR]

Published
2008
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6. Thermal-Hydraulic Analysis of the DTT Toroidal Field Magnets in DC Operation

Author

Andrea Zappatore, Aldo Di Zenobio, Roberto Bonifetto, Luigi Muzzi, Roberto Zanino, Simonetta Turtu, Bonifetto, R., Di Zenobio, A., Muzzi, L., Turtù, Simonetta, Zanino, R., and Zappatore, A.

Subjects
Test bench, Tokamak, Materials science, Nuclear engineering, Divertor, toroidal field magnet, modeling, Condensed Matter Physics, 01 natural sciences, DTT, nuclear fusion, thermal-hydraulics, Electronic, Optical and Magnetic Materials, law.invention, Thermal hydraulics, Physics::Plasma Physics, law, Shield, Magnet, 0103 physical sciences, Active cooling, Electrical and Electronic Engineering, 010306 general physics, Casing
Abstract

The Divertor Tokamak Test (DTT) facility is currently under design in Italy. This fully superconductive compact tokamak will be the test bench of several DEMO-relevant divertor solutions. The 4C code model of a DTT toroidal field magnet (including its structures) is developed here and used to support some important design decisions related to the neutron shield to be adopted, the need of an active cooling of the casing and the static heat load reduction. The simulations confirm the need to actively cool the casing by suitable cooling channels, but also the need of a proper neutron shield to reduce the nuclear heat load on the superconducting coils. On the other hand, the proposed static heat load reduction measures do not appear to be effective enough to satisfy the design requirement of 1.4 K for the minimum temperature margin.

Published
2020

10. Simulation of the ignition pulse in the small and large versions of the IGNITEX experiment.

Author

Montalvo, E., Carrera, R., and Rosenbluth, M.N.

Abstract

Summary form only given. Simulations of the time evolution of the discharge for the small and large versions of IGNITEX are presented. Fusion ignition requires that the ignition factor, defined as the alpha heating rate divided by the power loss, be larger than one. The ignition factor depends on density and temperature. The plasma should have enough excess power to be able to evolve from the low-temperature region at discharge start-up to the ignited region within the constraint of limited time imposed by the heating of the toroidal field magnet. This time is estimated as ≅6 s for the small version and ≅20 s for the large version. The time evolution of the ion, electron, and thermalized alpha densities and the ion and electron temperatures are described by a system of ordinary differential equations which is integrated over the plasma volume. Electrons are heated by the ohmic power and later in the discharge by the alpha particle energy deposition (considered instantaneous). Ions are heated by collisional interaction with electrons at the beginning of the discharge and directly from alpha particles later in the discharge. Energy losses include those by transport and radiation. The effect of the energy confinement scaling on the plasma conditions at the flat top of the discharge is studied. For neoalcator-type scaling laws, the thermal runaway is controlled by cyclotron radiation emission [ABSTRACT FROM PUBLISHER]

Published
1990
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11. Overview of Performance Test of Korean CICCs for ITER TF Magnet

Author

Young Jae Ma, Soun Pil Kwon, Pierluigi Bruzzone, Heekyung Choi, Boris Stepanov, Young Ho Seo, Soo-Hyeon Park, and Won Woo Park

Subjects
010302 applied physics, cable-in-conduit conductors, instrumentation, Thermonuclear fusion, Field (physics), Computer science, Nuclear engineering, Instrumentation, toroidal field magnet, Condensed Matter Physics, 01 natural sciences, Electronic, Optical and Magnetic Materials, Conductor, Acceptance testing, Magnet, ITER, numerical simulation, 0103 physical sciences, current sharing temperature, Electrical and Electronic Engineering, 010306 general physics, Electrical conductor, Voltage
Abstract

The Korean Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project has taken the responsibility of the procurement of cable-in-conduit conductors for the ITER toroidal field magnet. While procuring 27 conductor unit lengths, which are the Korean sharing, 10 conductors have gone through the superconducting performance test, under low temperature and high magnetic field, as one of the final acceptance tests. The sample assembly and instrumentation of various voltage taps and temperature sensors have been done according to the specified procedure, which had been agreed between domestic agencies and the ITER International Organization. The performance test program, which has also been agreed, was carried out. For the assessment of the current sharing temperature (Tcs), the standard analysis procedure has been adopted. Tcs of all samples, at 68 kA and a background field of 10.78 T, after 1000 cyclic current loads are well above the acceptance criterion. By analyzing the electric field as a function of temperature, the effective strain (eeff) and transition index (n-value) were reduced, and the behavior of eeff will be discussed in terms of the electromagnetic load, i.e., I × B. The effective strain was compared with the physical strain and results with a numerical simulation.

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