S. Entler

COMPARISON OF COOLING SCHEMES FOR HIGH HEAT FLUX COMPONENTS COOLING IN FUSION REACTORS

Some components of the fusion reactor receives high heat fluxes either during the startup and shutdown or during the operation of the machine. This paper analyzes different ways of enhancing heat transfer using helium and water for cooling of these high heat flux components and then conclusions are drawn to decide the best choice of coolant, for usage in near and long term applications.

Plans for Liquid Metal Divertor in Tokamak Compass

The COMPASS tokamak (R = 0.56 m, a = 0.2 m, BT = 1.3 T, Ip ~ 300 kA, pulse duration 0.4 s) operates in ITER-like plasma shape in H-mode with Type-I ELMs. In 2019, we plan to install into the divertor a test target based on capillary porous system filled with liquid lithium/tin. This single target will be inclined toroidally in order to be exposed to ITER-relevant surface heat flux (20 MW/m2). Based on precisely measured actual heat fluxes, our simulations predict (for 45° inclination, without accounting for the lithium vapor shielding) the surface temperature rises up to 700°C within 120 ms of the standard ELMy H-mode heat flux with ELM filaments reaching hundreds MW/m2. Significant lithium vaporization is expected. The target surface will be observed by spectroscopy, fast visible and infrared cameras. The scientific program will be focused on operational issues (redeposition of the evaporated metal, ejection of droplets, if any) as well as on the effect on the plasma physics (improvement of plasma confinement, L–H power threshold, Zeff, etc.). After 2024, a closed liquid divertor may be installed into the planned COMPASS Upgrade tokamak (R = 0.84 m, a = 0.3 m, BT = 5 T, Ip = 2 MA, Pin = 8 MW, pulse duration ~2 s) with ITER-relevant heat fluxes loading the entire toroidal divertor.

Interactive interoperability between firefighters and fire protection equipment

In 2005 coal handling bridges in Opatovice power station, Czech Republic, were damaged by fire. Effects of the fire limited coal supply for 3 months. Following that fire the new fire protection equipment have been gradually installed in other Czech power plants. In 2009 the complex automatic fire protection equipment of coal handling route was installed into operation in Tusimice power plant. However, after starting the operation it showed that activation of the extinguishing system on the inclined conveyor bridge threatened the health and life of fire-fighters conducting an intervention. In this paper an interactive algorithm that ensures a flexible cooperation intervening fire-fighters and automatic extinguishing system without a risk of fire-fighters life is investigated. To confirm the applicability of the interoperability algorithm possible fire scenario is analysed in NIST code FDS. Development of gas temperatures in strong chimney flow gives also a view into part of mechanical response of structure.