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[en] On a disruption with vertical displacement events (VDE), the three-dimensional (3-D) electromagnetic transient characteristics of in-vessel components in tokamak reactor have been studied numerically by using the finite element method. In this study, the in-vessel components are treated as the 3-D structure and the plasma halo region is modeled as the helical path of halo current can be treated. As a result, it is shown that there is difference in the electromagnetic stress of the divertor cassette between the current with helical path and the current with only the poloidal path. This difference is caused by the electromagnetic response of 3-D in-vessel components due to the helical path of halo current. It is essentially important for the design of tokamak reactors to treat the in-vessel components as the 3-D structure and to consider the helical path of halo current. (author)
[en] Conceptual design of an innovatively small tokamak reactor 'GNOME' based on a non-fission biomass-fusion hybrid concept is proposed. This fusion plant concept intends to use high-temperature heat from the blanket to generate hydrogen or synthetic fuels out of waste biomass. Since energy multiplication is expected by utilizing chemical energy of biomass, the requirement for the fusion plasma for net plant energy output is reduced to Q ≥ 5. As a result, the GNOME reactor has been designed to produce 320 MW fusion power with a 5.2 m major radius, 3.1 normalized beta and 11 T maximum field. This relatively small maximum field can be achieved by using Nb3Sn superconducting magnets. Besides, this reactor allows 3.0 m diameter space for its center solenoid coil and requires 60 MW of the input power. These features require minimal technical extensions from ITER.
[en] A tokamak with dimensional ratio A=2 was selected as a basis for the KTM project. Such tokamaks, having relatively small sizes, possess the predictable and controllable physical parameters, and allow realizing the conditions required for conduction of researches and testing of a wide range of structural materials. The tokamak vacuum chamber has a significant oblongness along the basic axis of the tokamak, which allows for placing a device with replaceable divertor plates inside the chamber. It also allows for equipping it with a transfer device that is capable of replacing the plates without disturbance of high vacuum. Besides, the tokamak will be equipped with limiters made of different materials, which also have different designs. It is also equipped with a first wall containment. The project envisages a first wall and intrachamber elements conditioning system. The tokamak is expected to be provided with a wide range of physical and technological diagnostics, which allows obtaining a required volume of the error-free information
[en] The KSTAR device succeeded in first plasma generation on 13th June of 2008 through comprehensive system test and commissioning. Among various kinds of the key factors that decisively affected the project, success in the construction and assembly of the major tokamak structure was most important one. Every engineering aspects of each structure were finally confirmed in the integrated commissioning period, and there were no severe troubles and failures prevented the KSTAR device from operating during the commissioning and the first plasma experiments. As a result, all of the experiences and technologies achieved through the KSTAR construction process are expected to be important fundamentals for future construction projects of superconducting fusion devices. This paper summarizes key engineering features of the major structures and of the machine assembly
[en] This paper explores dynamic monitoring and control solution targeting in-prototype hardware realization. Dynamic control strategy for tritium needs to be substantiated, developed, implemented, globally qualified (benchmarked) and certified according to ITER nuclear standards and regulations.
[en] The Atomic Fuels Division has initiated development and fabrication of Cable-In-Conduit-Conductor (CICC) of various configurations, for superconducting fusion grade magnets required for their indigenous Fusion Programme. The process involves development of high grade superconducting multifilamentary wire, multi stage cabling of superconducting as well as copper wires and, finally, jacketing of the cables in SS316LN tubes. The overview of the development and fabrication of CICC is presented in this article. (author)
[en] For estimation of tritium accumulation in first reactor wall is necessary now number of velocities values. In this work is analysed velocity values of the implantation, the dispersion, perambulating, adsorption, sorption etc. Candidate plasma-contacted materials in view its using for tritium accumulation estimate are presented. Model calculation of tritium accumulation on base known tokamak reactor velocities constants for different temperature zones are given