Showing papers in "Fusion Engineering and Design in 2000"

TL;DR: In this paper, a critical analysis is presented of the operating temperature windows for nine candidate fusion reactor structural materials: four reduced-activation structural materials (oxide-dispersion-strengthened and ferritic/martensitic steels containing 8-12%Cr, V-4Cr-4Ti, and SiC/SiC composites), copper-base alloys (CuNiBe), tantalum base alloys, and molybdenum and tungsten alloys.

TL;DR: In this paper, the authors compared the lifetime of coal, LWR fission, UP fusion, and wind power plants compared to the total amount of energy required to procure the fuel, build, operate, and decommission the power plants.

TL;DR: In order to obtain clear understandings of radiation damage in fusion materials, as well as the dynamic material behavior under severe environments in advanced energy systems, such as fusion reactors, fission reactors, a Multiple Beams-Material Interaction Research Facility (DuET facility) has been constructed at the Institute of Advanced Energy, Kyoto University, in these three years.

TL;DR: In this article, the authors report on recent research into magnetohydrodynamic (MHD) phenomena applicable to fusion technology and show that the maximum enhancement for liquid Lithium occurs for values of the interaction parameter in the N=10-20 range.

TL;DR: In this article, the authors extended previous studies on the rate of hydrogen induced disproportionation/reproportionation of ZrCo to a broader temperature range and compared them with protium and deuterium with the aim of determining possible isotope effect.

TL;DR: The ALPS program as mentioned in this paper was initiated in order to evaluate the potential for improved performance and lifetime for plasma-facing systems and demonstrate the advantages of advanced limiter-divertor systems over conventional systems in terms of power density capability, component lifetime, and power conversion efficiency, while providing for safe operation and minimizing impurity concerns for the plasma.

TL;DR: In this article, a localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR).

TL;DR: In this paper, a new shape reproduction method is investigated on the basis of an applied mathematical approach, where an analytically exact solution of Maxwell's equations in a static current field yields an (boundary) integral equation.

TL;DR: In this paper, a hybrid technique of chemical vapour infiltration (CVI) and polymer infiltration and pyrolysis (PIP) is proposed to fill the porosity among the fibres with SiC resulting from precursor decomposition.

TL;DR: An overview of the current status of the European R&D activities on SiCf/SiC composites focussing on reactor design studies, composites manufacturing, material characterisation in particular after irradiation, chemical compatibility with different blanket environments and development of joining techniques is presented in this paper.

TL;DR: In this paper, a reduced pressure electron beam (RPEB) welding was proposed for fusion vessel fabrication. But the work was performed on behalf of the UKAEA for the EU Task No. T301/1 (Fusion Reactor vessel fabrication).

TL;DR: In this paper, the Fusion Safety Program at the Idaho National Engineering and Environmental Laboratory (INEEL) has modified the MELCOR code in order to assess safety issues associated with loss of cooling accidents (LOCAs) and loss-of-vacuum accidents (LOVAs) in the international thermonuclear experimental reactor (ITER) engineering design activity (EDA).

TL;DR: In this article, the heat transfer parameters of a Li4SiO4 pebble bed have been measured at the Research Centre of Karlsruhe (Germany) with helium flowing through the bed at very low velocity.

TL;DR: In this paper, an interpretive equilibrium code CLISTE is proposed for the calculation of MHD equilibria on an intershot timescale, parallelized by the use of a Message Passing Interface (MPI).

TL;DR: In this paper, the ARIES-ST (Spherical Tokamak) is used to investigate the attractiveness of a low-aspect-device as the confinement concept for a fusion power plant.

TL;DR: In this paper, the authors collected and analyzed dust samples from three tokamaks to determine the potential contribution to accident source terms in future fusion power plants, including the tritium content of TFTR dust.

TL;DR: In this article, the authors describe the interaction between ceramic breeder and beryllium pebble beds and the structural material in ceramics, and present empirical correlations for the moduli of deformation for the different materials.

TL;DR: In this article, a preliminary conceptual design on high performance dual-cooled blanket of fusion-driven transmuter is presented based on neutronic calculation, which has some attractive advantages when utilized in transmutation of HLW (High Level Wastes).

TL;DR: The kinetics and mechnism of the hydrogen-induced disproportionation of ZrCo was studied experimentally in this article, showing that the disproportionation rate increased with increasing initial hydrogen pressure and showed a 3/2 power dependence on the pressure.

TL;DR: In this paper, experimental results of complex studies of lithium capillary-pore systems (CPS) for application as a plasma facing structure in divertor and on the first wall of a fusion reactor are reported.

TL;DR: In this article, the authors summarized the characteristics and performances of some potential candidate concepts for a European power plant study and associated required R&D, and summarized advantages and drawbacks of possible combinations of structural materials, coolants, and breeder materials.

TL;DR: In this article, a multi-pellet injector system has been developed as a fundamental fueling tool for the Large Helical Device (LHD), which has demonstrated continuous hundreds of injection without any fail and has been applied for the LHD experiment successfully.

TL;DR: In this paper, the authors present a review of the feedback control of plasma parameters using the three main digital control systems; the plasma position and current control system, the density feedback system and the real time central control system.

TL;DR: In this paper, the authors studied the plasma/material interaction in disruption simulation experiments at the plasma gun facility MK-200 UG, where graphite, tungsten and aluminium targets (beryllium-like material) were irradiated by intense plasma streams under heat fluxes typical for international thermonuclear experimental reactor (ITER) hard disruption.

TL;DR: In this article, the main issues related to the use of Be in a fusion reactor as both neutron multiplier and first wall material are discussed, including potential reactions with steam during accidents and the health and environmental aspects of its use, reprocessing and reuse, or disposal.

TL;DR: The ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio "spherical torus" (ST) plasma as discussed by the authors, which uses an advanced breeding blanket with flowing PbLi breeder and He-cooled ferritic steel structures.

TL;DR: In this paper, a 3D-CFC with high thermal conductivity (500 W/m per K), CVD technique for tungsten coating with 5mm thickness, oxygen free copper clad dispersion strengthened copper cooling tube (OFCu clad DS Cu), and joining technique between carbon fiber reinforced carbon composite (CFC) and copper alloy with silver-free braze have been developed.

TL;DR: In this article, a number of proven heat transfer enhancement techniques such as extended surfaces, swirl tape, roughening, porous media heat exchanger and particulate addition are reviewed.

TL;DR: The Active Gas Handling System (AGHS) of JET is continuously operated to provide torus fuelling and recycling of tritium in different chemical forms such as water, methane or molecular hydrogen as mentioned in this paper.

TL;DR: The main features of recent fusion reactor blanket conceptual designs using SiC f /SiC as structural material are presented in this article, with particular attention paid to the adopted safety and maintenance strategy.