Showing papers in "Fusion Engineering and Design in 2001"

TL;DR: In this paper, the authors explored novel concepts for fusion chamber technology that can substantially improve the attractiveness of fusion energy systems, including the potential for: (1) high power density capability; (2) higher plasma β and stable physics regimes if liquid metals are used; (3) increased disruption survivability; (4) reduced volume of radioactive waste; (5) reduced radiation damage in structural materials; and (6) higher availability.

TL;DR: The SiCf/SiC composite is a promising structural material candidate for fusion power cores and has been considered internationally in several power plant studies as discussed by the authors, but its behavior and performance at high temperatures and under irradiation are still not well known and need to be better characterized.

TL;DR: In this article, a hybrid magnet system for fast frequency tuning (1 s) is presented, where a water-edge-cooled silicon nitride composite Brewster window with its thermal conductivity of k=60 W/mK, permittivity er=7.35°, and clear window aperture of 100 mm diameter, will allow long-pulse operation in the 1 MW power range.

TL;DR: In this article, ITER Reference CRPP-ARTICLE-2001-037 was used as a reference for the ITER reference CRPP article, which was modified on 2017-05-12.

TL;DR: In this article, the use of high temperature superconductors (HTS) in long term tokamak fusion reactors is analyzed and the consequences of implementing an HTS configuration in a fusion environment are described.

TL;DR: In this article, the authors presented a prototype of a 1 MW/CW 140 GHz gyroron for ECRH heating of fusion relevant plasmas. But the performance of the prototype was not evaluated.

TL;DR: In this paper, the authors proposed a method that solves the above problem using a Monte Carlo code that allows a detailed geometry description, which requires modification of nuclear data library replacing a prompt gamma spectrum with a decay gamma spectrum and also a modest change in the computer program (MCNP).

TL;DR: In this article, the authors proposed a beam tracing method for short-wavelength electromagnetic wave beam propagation, in which the full wave equation is reduced to a set of ordinary differential equations that describe the behavior of the beam axis, the width of a beam and the curvature of the wave front.

TL;DR: In this paper, the production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing the fertile fuel with natural-UO2 and LWR (light water reactors) spent nuclear fuel.

TL;DR: In this paper, materials R&D for the vessel and in-vessel components have been performed in support of ITER design, and comprised the structural mate-rials (316L(N), CuCrZr, CuAl25, Inconel 718 andTi-alloys), plasma facing materials (Be, W andCFC), joints of stainless steel (SS), betweenSS/Cu alloys, Cu alloys/Be, Cu/W and Cu/CFC, and ceramic materials, (Al

TL;DR: In this article, the authors present a CVD diamond window for high power gyrotrons with a loss tangent in the region of 2 x 10 -5 at 145 GHz across the 80 mm clear aperture region of the disc.

TL;DR: In this paper, a hemispherical Fabry-Perot resonator was investigated for the determination of the mm-wave dielectric properties of CVD-diamond disks at elevated temperatures with the plane mirror locally heated and the specimen fixed to it.

TL;DR: In this paper, a 110 GHz 1 MW electron cyclotron range of frequency (ECRF) system was designed and constructed on JT-60U to locally heat and control the plasmas.

TL;DR: In this paper, the controllability of current profile driven by the fundamental resonance of the O-mode wave is examined for the parameters of the IASM option of the International Thermonuclear Experimental Reactor (ITER).

TL;DR: In this paper, a 110 GHz-Gaussian beam output gyrotron with chemical vapor deposition (CVD) diamond window was developed for electron cyclotron heating and current drive on JT-60U.

TL;DR: In this article, an ECH system consisting of 0.5 MW, 84 GHz range and 168 GHz gyrotrons, high voltage power supplies, long distance transmission lines, and invessel quasi-optical antennas was developed and constructed.

TL;DR: In this article, the problem of electron temperature measurement in plasmas where the Maxwellian shape of the electron distribution function has been distorted at low energies (in the thermal range) is investigated.

TL;DR: In this article, the development of welding, cutting and non-destructive testing (NDT) techniques have been carried out for on-site manufacturing and maintenance of the thick-wall structure of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV).

TL;DR: In this article, a large helical device (LHD) experiment was conducted with six gyrotrons whose frequencies are 82.6/84 and 168 GHz, respectively, and up to 0.9 MW power was injected in LHD with long distance corrugated waveguide transmission systems, and the maximum pulse width was achieved to 3.0 s/240 kW for the LHD experiments.

TL;DR: The 140 GHz ASDEX-Upgrade ECRH system as discussed by the authors uses four gyrotrons to generate a total power of 2 MW in a Gaussian beam for 2 s. External magnetic perturbations, originating from the poloidal stray magnetic field of the tokamak air core transformer and also from the cryomagnet of the adjacent gyrotron, influence the startup of the oscillation and the electron beam deposition in the collector.

TL;DR: NSTX is a proof-of-principle experiment aimed at exploring the physics of the ‘spherical torus’ (ST) configuration, which is predicted to exhibit more efficient magnetic confinement than conventional large aspect ratio tokamaks, among other advantages.