[en] In this paper, by extrapolating the experimental laws describing the energy confinement and the magnetohydrodynamic stability limits in current large tokamaks, it is shown that stable thermonuclear ignition equilibria should exist in this type of configuration if the aB_t^x product of dimensions multiplied by a power of the magnetic field intensity is large enough. By quantitatively applying this result to several next- generation tokamaks, it appears that such equilibria could exist in these machines. Moreover, the additional heating power that will be available in these devices should be sufficient for ignition

[en] The small Canadian program of research on nuclear fusion is featured at a popular level. The main facilities are the Tokamak de Varennes, a small Tokamak at the University of Saskatchewan, and a facility for research on fusion fuel and blanket technology at Chalk River. The program is coordinated as regard federal funding and international cooperation by a group at Chalk River

[en] This paper reports on the next generation of tokamaks, ITER or BPX, which will be characterized by an even greater emphasis on joint operation and experimentation. With anticipation of an increased number and diversity of collaborations, preparations for such shared facilities by developing a systematic approach to remote, joint physics operation involving experimental teams at several locations are underway. The local area network of computers used for control and data acquisition on present and future experimentrs can be extended over a wide area network to provide a mechanism for remote operation of subsystems required for physics experiments. The technoloy required for high bandwidth (≥45Mbps) connections between multiple sites either exists or will be available over the next few years. With the rapid development of high performance workstations, network interfaces, distributed computing, and video conferencing, the authors can proceed with the development of a system of control and analysis sites to provide for consistent, efficient, and continuing collaborations. Early establishment of such sites could also enhance existing joint design and development efforts

[en] A parametric study to determine the optimal range of tokamak parameters for the breeder has been performed. Most of the technology required is already available in the world, but it has still to be developed in India. Hence two different options have been considered. The first is a reactor with a low fissile production rate (FPR=few kg/yr). The emphasis is on reducing cost and simplifying design. The device will demonstrate the feasibility of fusion breeders and should be achievable within a moderate time span. Its design and operation will give valuable experience in combining diverse technologies, but it is not intended as a commercial breeder. The second option is a scale up of this device. It will have a moderate FPR (few hundred kg/yr), and will take more time to develop. The increase in energy gain will come from an increase in size and greater complexity in design. Given time, most of the components could be developed in India. Some intermediate steps will be necessary between current tokamak ADITYA and the final device, to allow enough time for developing new technologies. The results of the parametric study for both options, and the optimal parameters of the intermediate steps are presented. (author). 7 refs., 2 tabs

[en] Thorium is one of the most promising hybrid blanket materials for breeding nuclear fuel for the fission reactors. Some integral experiments to examine the nuclear data of thorium for further investigation of hybrid blanket designs are being conducted. Gold foils and aluminium foils were irradiated with neutrons by means of the D-T neutron generator at the Kyoto University Critical Assembly. Reaction rate was deduced from ¹⁹⁸Au and ²⁴Na activities measured with a 50 cm² pure Ge detector. The time of flight measurement was performed by using an associate particle method. The associated alpha signals from a thin plastic scintillator were used to trigger the time analyzer. Measured reaction rate and measured spectrum were compared with those calculated with MNCP Monte Carlo code and JENDL-3 and ENDL-75 data files. (author). 10 refs., 7 figs

[en] The author summarizes (i) the updating of the H mode database; (ii) new experimental devices; (iii) next step devices; (iv) reactor studies; (v) stellarators; (vi) inertial confinement reactors, and (vii) the technology of next step devices and reactors

[en] Considering that a thinner blanket and smaller inboard space is required in a D-³He fueled tokamak reactor which produces much lower neutron wall loading so that maintenance problem may not be so serious, the author adopts low aspect ratio tokamak to obtain better plasma shaping and be in favour of current drive, hence higher beta and better confinement. Based on the current basic plasma physics, a DHE3TOK code was developed. A scoping analysis of D-³He fueled tokamak operating in first stability regime with low aspect ratio A = 2.5 has been performed. An extensive survey of operating physical parameters has been carried out and some features of D-³He commercial reactor are discussed

[en] The JET tokamak device and all other installations could be built and completed to a large extent within the given time and cost frame. The study presented gives an appraisal of the scientific programme management of the JET undertaking and discusses proposed items of the scientific work programme to follow, together with the line of development from JET to the 'Next Step'. The project administration is discussed, stating key problems and conclusions drawn from experience gained so far. (orig.)

[en] The paper presents an overview of the remote handling experience acquired in various fields of applications and comments on its applicability to the fusion environment. The review of the general requirements for remote handling equipments operating in the future fusion reactors is presented. The particular constraints are highlighted which are principally represented by the very high radiation fields and the contamination problems. The fusion reactor maintenance activity is rather unique in the frame of nuclear activities, this is the first time such important structures will be almost entirely maintained by robotic means. The experience in other domains of activities is generally transferable at the conceptual levels (principles and organisation) however at the components levels the situation is more difficult due to the very stringent environment constraints. The components (motors, sensors, cameras, manipulators, toolings) will be applicable with some adaptations but the large structures (transporters, transfert systems) will have to be designed specifically. Among the others, the experience gained in the reprocessing community is particularly for fusion. (orig.)

[en] At the Joint European Torus (JET) nuclear fusion research project in the UK, two precise holes had to be cored in concrete and blockwork up to 2.8 m thick. Diamond drilling offered the only means of completing the work in the time available, with the required precision and while maintaining clean working conditions for scientific equipment in the vicinity. The details of the drilling operation are reported in this article. (author)