[en] The operating conditions in fusion power reactors will be extremely severe. Materials which can be exposed to neutron fluences of the expected order of magnitude (200 dpa) without drastic changes in their properties, are not yet available. The existing alloys which are currently considered for further development do not comply with the conditions for low activation materials. Both conditions ask for the development of new materials. In order to meet the present time schedule for the design and construction of a DEMO fusion reactor. A strategy has to be designed how the development should be organised, how the irradiation data for high fluences can be derived by extrapolation from data which can be obtained in existing facilities, which new facilities are necessary, and how the data collection for the engineering design should be assembled. (orig.)

[en] Experimental research on molten salt thermofluid technology using a high-temperature molten salt loop (MSL) is described in this paper. The MSL was designed to be able to use Flibe as a coolant, however, a simulant, heat transfer salt (HTS) has to be used alternatively since Flibe is difficult to operate under avoiding a biohazard of Be. Experiment on heat-transfer enhancement, that is required for applying to cool the high heat flux components of fusion reactors, is ongoing. Preliminary experimental results showed that an internal structure of a mixing chamber in the MSL was important to obtain accurate bulk temperatures under severe thermal conditions. For operating the loop, careful handling are needed to proceed how to melt the salt and to circulate it in starting the operation of the MSL. It is concluded that several improvements proposed from the present experiences should be applied for the future Flibe operation

[en] The proceedings and results of the 1st IAEA research Coordination Meeting on ''Tritium Retention in Fusion Reactor Plasma Facing Components'' held on October 5 and 6, 1995 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of presentations made by the meeting participants, the results of a data survey and needs assessment for the retention, release and removal of tritium from plasma facing components, a summary of data evaluation, and recommendations regarding future work. (author). 4 tabs

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[en] The present invention provides a thermonuclear device, in which integrity of a measuring device is kept, the reactor wall temperature and wear of armour materials are monitored accurately even under intense radiation rays, so that the flow rate of coolants and plasma power can be controlled by using the signals. Infrared rays generated from the surface of the armour materials disposed on a first wall are detected to measure the reactor wall temperature. Coolant flow rate and plasma power are controlled based on the obtained reactor wall temperature. In addition, infrared rays generated from the back of the armour materials are detected to obtain the surface temperature in order to avoid intense radiation rays from plasmas. The coolant flow rate and the plasma power are controlled based on the obtained temperature on the surface of the reactor thereby controlling the temperature of the first wall and the armour material to 300degC or lower in a case of the first wall made of stainless steel and 1000degC or lower in a case of the armour material made of graphite. (I.S.)

[en] The conceptual design of a Tokamak fusion power reactor, UWMAK-II with a special emphasis on the superconducting magnet designs is described. The reactor is designed to generate 5000 MW(th) during the plasma burn and to deliver 1716 MWsub(e) continuously. The structural material is 316 stainless steel and the primary coolant is helium. UWMAK-II is a low aspect ratio, low magnetic field design and includes a double null, axisymmetric poloidal field divertor for impurity control. In addition, a carbon curtain, made of two-dimensional woven carbon fiber, is mounted on the first vacuum chamber wall to protect the plasma from high Z impurities and to protect the first wall from erosion by charged particle bombardment. The blanket, which is designed to minimize the inventory of both tritium and lithium, utilizes a solid breeding material (LiAlO₂) with beryllium as a neutron multiplier. The total energy per fusion is 21.56 MeV, which is fairly high. The UWMAK-II toroidal field (TF) magnets are a set of 24 'extended D' superconducting coils of TiNb in Cu with stainless steel structure. The shield can be opened and a blanket module removed between coils without removing the TF coils. The vertical field (VF) coils have been deliberately placed inside the TF coils to minimize the energy stored in the poloidal magnetic field. The design philosophy for the VF coils is crucial when they are placed inside the TF set and this is discussed in detail. Toroidal coil design is discussed as based on a simple analytic solution for a constant tension 'D' sector. Magnet protection and safety circuits are described

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[en] The following six papers represent a cross section of the invited presentations made in two special sessions at the 1982 Winter Meeting of the American Nuclear Society (ANS) in Washington, D.C., on the subject of ''Radioactivation of Fusion Structures.'' Additional papers from these special sessions are expected to be published in a forthcoming issue of this journal. Plans for this ''minisymposium'' originated within the ANS Isotopes and Radiation Division and were carried forward in collaboration with members of the ANS Fusion Energy, Radiation Protection and Shielding, and Materials Science and Technology Divisions. As the program for these sessions crystallized, it became apparent that the theme, ''Radioactivation of Fusion Structures,'' might be too narrowly conceived and perhaps should include the coolant-breeder system. This broader viewpoint in fact was adopted in some of the papers

No abstract available