Abstract
ITER diagnostic first walls (DFWs) and diagnostic shield modules (DSMs) inside the port plugs (PPs) are designed to protect diagnostic instrument and components from a harsh plasma environment and provide structural support while allowing for diagnostic access to the plasma. The design of DFWs and DSMs are driven by 1) plasma radiation and nuclear heating during normal operation 2) electromagnetic loads during plasma events and associate component structural responses. A multi-physics engineering analysis protocol for the design has been established at Princeton Plasma Physics Laboratory and it was used for the design of ITER DFWs and DSMs. The analyses were performed to address challenging design issues based on resultant stresses and deflections of the DFW-DSM-PP assembly for the main load cases. ITER Structural Design Criteria for In-Vessel Components (SDC-IC) required for design by analysis and three major issues driving the mechanical design of ITER DFWs are discussed. The general guidelines for the DSM design have been established as a result of design parametric studies.
Highlights
ITER diagnostic first walls (DFW) and diagnostic shield modules (DSM) mounted inside the port plug structure are designed and installed to protect diagnostic instrument and components from a harsh plasma facing environment
The design of DFWs is largely driven by the high heating rate during normal plasma operation as well as large electromagnetic (EM) loads during plasma major disruptions and Vertical Displacement Events (VDEs).[5,6]
Since DFWs are attached to the DSM at the tabs via bolted joints, the design and analysis of the DFW and DSM is directly coupled with interface thermal and EM load transfer at the tab
Summary
ITER diagnostic first walls (DFW) and diagnostic shield modules (DSM) mounted inside the port plug structure are designed and installed to protect diagnostic instrument and components from a harsh plasma facing environment. The port plug assembly provides necessary structural support of diagnostic systems while allowing diagnostic access to the plasma.[1,2] The DFW design is challenging due to the conflicting set of requirements for diagnostics protection from high plasma heating and nuclear radiation while allowing diagnostic viewing access.[3] Figure 1 shows the upper and equatorial port plugs inside ITER Tokamak.[3] All 6 first walls in an equatorial port can be different due to Figure 1. Since DFWs are attached to the DSM at the tabs via bolted joints, the design and analysis of the DFW and DSM is directly coupled with interface thermal and EM load transfer at the tab. Details of the attachment tab design and bolt selection, as well as impact of DSM attachment system to DFW and PP structure will be presented in future papers
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