[en] The work carried on by the FINTOR (Frascati, Ispra, Napoli, Tokamak Reactor) group has now reached a stage where the effects of the main physics and engineering constraints, for a minimum size Tokamak Experimental Reactor have been clearly identified. This phase, now completed, has allowed to produce a self-consistent design of each basic component of the reactor, FINTOR 1, and to identify the more relevant interface problems toward a further optimisation of the reactor dimensions and characteristics to be performed in the future (FINTOR 2)

[en] We may identify two main areas where auxiliary heating may be used in breakeven Tokamak reactors. (1) In the start up phase of a Tokamak reactor, having a thermal energy distribution, auxiliary heating is required to bridge the gap between the ohmic state where the temperature will probably be approximately 1 keV, and the ignited condition where T>5 keV. (2) In two component and three component systems, auxiliary power is required to maintain a non-thermal ion distribution. I will follow a similar line to that taken in the above papers and will assess the auxiliary heating requirements of a 'Breakeven Tokamak' producing approximately 500 MW of thermal power, using the D-T cycle. I will consider two and three component systems insofar as they may be used during the start up phase, but not as reactor systems in their own right. In the first lecture I will not discuss details of the heating methods. Symbols and units are given in the Appendix

[en] In this short lecture, only two types of reactors will be discussed: the liquid metal fast breeder reactors (LMFBR) and the high temperature reactors (HTR). This does not mean that other very interesting concepts do not exist, but there are or proven light water reactors and heavy water reactors or has not reached the state of industrial development like molten-salt or gas breeder reactors. In discussing any types of industrial development, it seems to me useful, first to indicate the reasons or motivations for this development. Then I will give a short historical review and analysis of what has been done up to now. For HTR's a very brief status report will be presented. For LMFBR's, I will give indications of experience gained with demonstration plants and more specifically with Phenix, before listing the most important technical problems which still need more work to be fully solved. Finally, I will briefly discuss the economic status and perspectives of LMFBR's and will mention the public acceptance problem

[en] A PDFD will operate in the 1980's and must provide the plasma and plasma support technology information necessary to warrant design, construction, and operation of succeeding experimental power reactors and then the demonstration plant. The PDFD must be prototypical of economic fusion devices to justify its cost. Therefore, development of the fusion core will be the focus of the PDFD. The physics performance, power production objectives, and characteristics of the PDFD, and their relationship to the research and development needs to achieve them are outlined. The design criteria for a PDFD which satisfied these constraints will be established

[en] Proceeding from a reasonable agreement with existing experimental results, this lecture presents radial particle and energy transport computations which extrapolate to large (up to reactor dimensions) future Tokamaks. Special consideration is given to the behavior of alpha-particles, the influence of high-z impurities, and the thermal stability of the plasma

[en] The plasma wall interactions for two extreme cases, the 'vacuum model' and the 'cold gas blanket' are outlined. As a first step for understanding the plasma wall interactions the elementary interaction processes at the first wall are identified. These are energetic ion and neutral particle trapping and release, ion and neutral backscattering, ion sputtering, desorption by ions, photons and electrons and evaporation. These processes have only recently been started to be investigated in the parameter range of interest for fusion research. The few measured data and their extrapolation into regions not yet investigated are reviewed

No abstract available

[en] The environmental problems related to the use of large quantities of tritium are reviewed. Particular attention is given to the health physics aspects arising from chronic and acute exposures to tritium, and to permissible release rates from large fusion devices. It is concluded that damage to man, including mutagenic effects, resulting from tritium intake is sufficiently known for maximum permissible dose rates to be defined, and that routine release rates from a stack of the order of 1000 Ci/y would not lead to dose rates to the public in excess of permissible limits. The technologies required in large fusion devices, like the experimental power reactor, are commented with a view on the future European fusion programme, emphasizing the need for research and development in the areas of tritium recovery from the exhaust and from the blanket, of tritium containment and waste disposal. Finally, licensing problems are discussed, suggesting a few supplementary points, insufficiently covered in the present or in the forthcoming regulations, especially those related to the transport and to the disposal of tritium wastes

[en] There is one design requirement which appears to be common to all D-T fusion reactors, irrespective of the plasma confinement principle embodied in the design. It must be practicable to repair the structure or 'first wall' nearest the plasma. A repair can include a range of operations between finding and sealing a pinhole leak in a weld to complete replacement of the whole structure of the breeding blanket. The two reasons why these repairs are necessary are: 1) The variability and defects in generally perfect products, such as those caused by errors of human performance or by flaws in raw materials. 2) The extreme severity of the environment of the first wall, which causes the deterioration of the properties of materials situated there. This deterioration is the result of neutron irradiation and transmutation in the materials under conditions of stress and high temperature and of surface corrosion and erosion

[en] This Fusion Power Program Plan treats the technical, schedular and budgetary projections for the development of fusion power using magnetic confinement. It was prepared on the basis of current technical status and program perspective. A broad overview of the probable facilities requirements and optional possible technical paths to a demonstration reactor is presented, as well as a more detailed plan for the R and D program for the next five years. The 'plan' is not a roadmap to be followed blindly to the end goal. Rather it is a tool of management, a dynamic and living document which will change and evolve as scientific, engineering/technology and commercial/economic/environmental analyses and progress proceeds. The use of plans such as this one in technically complex development programs requires judgment and flexibility as new insights into the nature of the task evolve. The presently-established program goal of the fusion program is to develop and demonstrate pure fusion central electric power stations for commercial applications