[en] This document records the assumptions under which the ITER Fuel Systems cost estimates were prepared. These are order of magnitude estimates, obtained without flow sheet or detailed equipment analysis by applying factors, ratios, and escalation to the known cost of an installation considered to be similar. The estimates include equipment and installation costs for each component. (5 figs., 16 refs.)

No abstract available

[en] A computerized database storage and retrieval system has been set up for fusion devices and the associated fusion fuel systems which should be a useful tool for the CFFTP program and other users. The features of the Wang 'Alliance' system are discussed for this application, as well as some of the limitations of the system. Recommendations are made on the operation, upkeep and further development that should take place to implement and maintain the system

[en] This document identifies the primary sources of power requirements, and records the assumptions under which the Fuel Systems power consumption was estimated and balanced. (2 tabs., 15 refs.)

[en] We report on the first realisation of an efficient inboard pellet launch for controlled plasma refueling at reactor grade levels. Inboard pellet launch is performed via a flexible teflon guiding tube mounted inside the torus vessel, coupled to the centrifuge by an aluminium funnel. With this setup, pellet injection velocities up to 400 m/s and rates up to 60 Hz were achieved with a reliability beyond 91%. A pellet induced plasma particle inventory increase was found to be in the range of 0.25 to 0.4 times the ideal pellet mass. Pellet particle fluxes up to 10²²/s were achieved, more than sufficient for a rapid density increase in ASDEX Upgrade and a stable, controlled operation at densities beyond the empirical Greenwald limit. (authors)

[en] The invention is referred to devices for fuel injection into magnetic mirrors and can be used when developing and constructing large thermonuclear devices. The invention is aimed at increasing the efficiency of preserving the initial distribution of plasma density in a thermonuclear device. For this purpose at least two plates in the plate package of an accelerating device have different thickness. The injected pellets produced on plates with different masses. Pellets with large mass are injected to the plasma volume slower which leads to a more than linear increase of its ablation rate. Their evaporation is more efficient. Pellets injected from plates with different thickness supply fuel to different parts of plasma volume which facilitates a more efficient upkeep of initial plasma density distribution in a thermonuclear device. 3 figs

[en] Technique for pellet feeding into the accelerating channel of macroparticle injector rotor by pellet transportation perpendicular to the accelerating channel and its catching by this channel is described. The aim of invention is to increase feeding reliability, to eliminate pellet losses and to reduce their scattering angle at the output from the accelerating channel

[en] A pellet injector of new type with accurately and continuously controllable system of pellet size has started to be developed. This has a unique mechanics and structure of producing a frozen pellet in extremely low temperature region. In the device presently developed in this research, we will precisely adjust the length of the cylindrical pellet (diameter 1.0 mm) from 0.5 to 3 mm by using the special 'length limiting rod' system

[en] Within the frame of the Engineering Design Activity phase of ITER a concept of an Automated Control System (ACS) for the Tritium Plant has been defined in Karlsruhe and a detailed cost estimation been carried out. This paper outlines the ACS and draws attention to important points to be i) met in plant design and construction, and ii) defined in specifications, so as to create the preconditions underlying the cost estimates and achieve a satisfactory interaction between the ACS and the Tritium Processing Systems. (authors)

[en] The Tritium Systems Test Assembly (TSTA), a full size simulation of the fuel loop for a fusion reactor, will circulate 360 g mol/day (1800 g) of DT and will have an inventory of 150 g of tritium. During shutdown, a safe storage system for hydrogen isotopes, primarily DT, is needed. Uranium reacts readily with hydrogen, deuterium, or tritium at room temperatures to form U(H, D, T)₃ having a dissociation pressure of approximately 10^-4 Torr. Upon heating to 720 K, the isotopes will desorb at pressures of 1 to 2 atm. Uranium beds were selected as the means for long-term storage of the fuel loop inventory