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Chinju, South Korea

Nam K.,National Fusion Research Institute | Park H.,National Fusion Research Institute | Kim D.,National Fusion Research Institute | Bae J.,National Fusion Research Institute | And 4 more authors.
Fusion Engineering and Design | Year: 2015

The ITER upper port stub extension (UPSE) of the vacuum vessel (VV) is classified into 2 categories according to its location and time to install; one is the central (even) UPSE which is welded at upper central position of the VV sector and delivered after attached to VV at factory. The other is the lateral (odd) UPSE which is welded at upper lateral position of the VV sector and the significant difference with the central UPSE is that the lateral UPSE is welded after whole VVs welded because this should be installed between adjacent VVs at Tokamak in-pit. The design of the dedicated assembly tool for the UPSE assembly has been developed by the Korean domestic agency (KODA). Adjustment system of this assembly tool has been also designed to meet the functional requirements requested by IO. For design verification of the UPSE assembly tool mentioned above, a mock-up has been fabricated in full size and tested according to the UPSE functional requirements for the assembly procedure. And the structural analysis results of the current design will be presented also. © 2015 Elsevier B.V. Source


Noh C.H.,National Fusion Research Institute | Chung W.,National Fusion Research Institute | Nam K.,National Fusion Research Institute | Kang K.-O.,National Fusion Research Institute | And 7 more authors.
Fusion Engineering and Design | Year: 2015

The thermal shield (TS) provides the thermal barrier in the ITER tokamak to minimize heat load transferred by thermal radiation from the hot components to the superconducting magnets operating at 4.2. K. The TS is actively cooled by 80. K pressurized helium gas which flows from the cold valve box to the cooling tubes on the TS panels via manifold piping. This paper describes the manifold piping design and analysis for the ITER thermal shield. First, maximum allowable span for the manifold support is calculated based on the simple beam theory. In order to accommodate the thermal contraction in the manifold feeder, a contraction loop is designed and applied. Sequential Quadratic Programming (SQP) method is used to determine the optimized dimensions of the contraction loop to ensure adequate flexibility of manifold pipe. Global structural behavior of the manifold is investigated when the thermal movement of the redundant (un-cooled) pipe is large. © 2015 Elsevier B.V. Source


Kim K.-K.,Mecha T and S | Noh C.H.,National Fusion Research Institute | Kim Y.-K.,Mecha T and S | Park S.,Mecha T and S | And 6 more authors.
Fusion Engineering and Design | Year: 2016

The ITER thermal shield is actively cooled by 80. K pressurized helium gas. The helium coolant flows from the cold valve box to the cooling tubes on the TS panels via manifold piping. This paper describes the final design of thermal shield manifold. Pipe design to accommodate the thermal contraction considering interface with adjacent components and detailed design of support structure are presented. R&D for the pipe branch connection is carried out to find a feasible manufacturing method. Global structural behavior and structural integrity of the manifold including pipe supports are investigated by a finite element analysis based on ASME B31.3 code. Flow analyses are performed to check the flow distribution. © 2016 Elsevier B.V. Source

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