Heejin Shim , Jaemin Kim , MunSeong Cheon , Sunil Pak
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引用次数: 0
Abstract
Upper Port #18 (UP18) is one of the ITER Diagnostic Ports located at the upper position of the Vacuum Vessel (VV). A key aspect of the ITER research program is the diagnosis of the plasma and the first-wall, such as plasma temperature, density and radiative properties. For this purpose, a variety of diagnostic equipment peers into the ITER VV from many different vantage points. The main function of this port integration system is to host and locate tenant diagnostics while provide apertures for diagnostic viewing access to the plasma.
The upper port plug assembly is composed of three main structure; the Upper Port Plug (UPP) structure, Diagnostic First Wall (DFW) and Diagnostic Shield Module (DSM). The UPP structure is common to all diagnostic upper ports and serves as a base platform for in-vessel integration. The DSM is one of the key parts of the port plug, the DSM of UP18 should be integrated using the generic modular DSM design. This generic modular DSM needs to be customized to integrate each tenant diagnostic system according to their specific requirements. UP18 hosts three tenant diagnostic systems; the Neutron Activation System (NAS), the Vacuum Ultra-violet (VUV) system, and the Upper Vertical Neutron Camera (UVNC). The DSM of UP18 has precise cut-outs to host those tenant systems and provides a Line of Sight (LOS) in the form of a narrow deep opening for measuring plasma behavior under extreme conditions.
This paper focuses on the manufacturability assessment of the simplified full-scale prototype of the DSM structure and the feasibility of electron beam welding assembly to finalize the upper port assembly design through the entire manufacturing process, including dimensional inspections.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.