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The subassembly procedure and relevant tools for the complete 40^\circ sector assembly as a foundation of the ITER machine have been developed to meet technical and functional requirements for years. Based on the concept of subassembly procedure and tools provided by ITER Organization, detailed procedure and relevant purpose-built assembly tools are developed by Korea Domestic Agency. The tools described in this paper contain an upending tool, a lifting tool, a sector subassembly tool, and a radial beam and vacuum vessel supports with alignment units. To verify the 6-degree-of-freedom system for fine alignment of components in the sector subassembly tool, scale-down mock-up has been manufactured and tested. This paper presents the overall 40^\circ sector subassembly procedure, the fundamental specifications of the relevant assembly tools, and the current status of the mock-up developments. [ABSTRACT FROM PUBLISHER]

Abstract: The purpose-built, ITER tokamak assembly tools, which are to be provided by Korea, should be designed to meet: the assembly plan, space reservations, safety standards, simple operations, efficient maintenance, and so on. It is very important that the ITER assembly tools are able to lift and transfer ITER components or their sub-assemblies to their assembled position safely. Furthermore, the lifting tools will lift and handle very heavy loads that can be more than 1200 tonnes sometimes. Therefore, the ITER lifting tools must be designed to endure these heavy load conditions with regard to their structural integrity. Also, these designs should be verified through an appropriate method. The preliminary design of the sector lifting tool and associated lifting attachments are introduced in this paper. The sector lifting tool was designed especially to lift and handle various ITER components by adjusting the lifting centre. The structural analysis results using ANSYS are described considering the heaviest load condition. The results of the analysis show that; all stresses applied on the lifting tool are lower than the allowable stress of the applied material. [Copyright &y& Elsevier]

Abstract Korea has own programs toward DEMO and fusion reactors that will require further improved DEMO blanket and energy utilization systems. Primary goals of DEMO blanket development in Korea are to develop and verify the integrated blanket design tools; to develop blanket materials, cooling and tritium fuel cycle technologies; and to develop and evaluate fabrication and joining technologies. The concept of helium-cooled ceramic reflector (HCCR) blanket is adopted to be tested in ITER as Test Blanket Module (TBM). Currently, the design and R&D activities are mainly performed through the ITER TBM program in Korea. It is expected to demonstrate the major objectives of the breeding blanket: extraction of heat from burning plasma, tritium self-sufficiency and its integrity within the whole systems considering safety features. Although TBM program will provide very essential data and experience, there will be a considerable technical gap from DEMO blanket. This paper presents the technical gap in the main technical categories of the breeding blanket based on the experience of the development of HCCR TBM and breeding blanket. It is found that still about 60–70% of the DEMO blanket technology can be achieved through the HCCR TBM depending on the technology maturity level, and some ways to DEMO blanket from HCCR TBM are proposed. [ABSTRACT FROM AUTHOR]

Abstract: As the ITER is being constructed, there is a growing anticipation for an earlier realization of fusion energy, so called fast-track approach. Korean strategy for fusion energy can be regarded as a fast-track approach and one special concept discussed in this paper is a two-stage development plan. At first, a steady-state Korean DEMO Reactor (K-DEMO) is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used as a component test facility. Then, at its second stage, a major upgrade is carried out by replacing in-vessel components in order to show a net electric generation on the order of 300MWe and the competitiveness in cost of electricity (COE). The major radius is designed to be just below 6.5m, considering practical engineering feasibilities. By using high performance Nb3Sn-based superconducting cable currently available, high magnetic field at the plasma center above 8 T can be achieved. A design concept for TF magnets and radial builds for the K-DEMO considering a vertical maintenance scheme, are presented together with preliminary design parameters. [Copyright &y& Elsevier]

Abstract: ITER sector assembly tools are customized tools for final integration of nine 40° sectors sub-assembled at assembly building and ex-vessel components. These tools include a central column, radial beams and their supports, assembly tools for poloidal field (PF) coils, and pre-compression ring (PCR) assembly tools and so on. The central column was designed to have sufficient strength to support nine 40° sectors and adjustment function of toroidal field coil (TFC). The PF assembly tools were designed also to support temporarily PF5 and 6 coils during sectors assembly duration, and to assembly PF coils to designated position with synchronized lifting and adjustment functions. Synchronized system applied to hydraulic cylinders of TF inner adjustment device and PF coil assembly tools is the key function to make highly precise assembly at final positioning. Hence, mock-ups were fabricated and tested to verify synchronized system of TF inner adjustment device and PF assembly tools. As results of tests, synchronized system operated by solenoid valves and linear sensors was verified to have high-resolution for final assembly of TFC and PF coils. [Copyright &y& Elsevier]