Analysis of the processes in the target cooling system of the W7-X fusion experiment
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T. Kaliatka
Abstract
Nuclear fusion has the potential to cover a major part of mankind's energy needs under the conditions of ever-increasing population and energy consumption. Wendelstein 7-X (W7-X) is a fusion experiment currently being built in Greifswald, which shall demonstrate the capability of the stellarator concept on the way to a fusion power plant. This paper presents analyses of processes in the target cooling system with the codes RELAP5 and ASTEC. The loss-of-coolant accident (LOCA) during the “baking” operation mode of W7-X (i.e. under the most critical conditions because of the high temperature and pressure applied) is analysed. The response of the W7-X “baking” and main cooling circuits and the amount of coolant discharged into the plasma vessel are investigated.
Kurzfassung
Die kontrollierte Kernfusion hat das Potential unter der Bedingung eines ständig wachsenden Energiebedarfs der zunehmenden Weltbevölkerung die langfristige Energieversorgung der Menschheit abzusichern. Das Fusionsexperiment Wendelstein 7-X (W7-X), welches zurzeit in Greifswald (Deutschland) aufgebaut wird, soll die Eignung des Stellarator-Konzepts für ein zukünftiges Fusionskraftwerk nachweisen. In dieser Arbeit werden die Prozesse im Wasser-Kühlsystem der Fusionsanlage W7-X mit Hilfe der Simulationsprogramme RELAP5 und ASTEC analysiert. Während der aufgrund der hohen Temperaturen und Drücke kritischen W7-X Betriebsphase ”Ausheizen“ wird ein Kühlmittel Verlust bei einem Leck betrachtet. Die entsprechenden Reaktionen des Wasser-Kühlkreises ”Ausheizen“ und des Haupt-Kühlkreislaufes werden untersucht und die Leckagemenge ermittelt, die dabei in das Plasmagefäß einströmt.
References
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© 2010, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
- Analysis of the processes in the target cooling system of the W7-X fusion experiment
- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
- Targetry of Y2O3 on a copper substrate for the non-carrier-added 89Zr production via 89Y(p, n)89Zr reaction
