Multiphysics Engineering Analysis for an Integrated Design of ITER Diagnostic First Wall and Diagnostic Shield Module Design

Journal Article · Wed Jul 01 04:00:00 EDT 2015 · Fusion Science and Technology

DOI:https://doi.org/10.13182/fst15-103· OSTI ID:1256633

Zhai, Y. ^[1]; Loesser, G. ^[1]; Smith, M. ^[1]; Udintsev, V. ^[2]; Khodak, A. ^[1]; Johnson, D ^[1]; Feder, R ^[1]

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1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
2. ITER Org, F-13115 St Paul Les Durance, France.

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.

• Research Organization: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC02-09CH11466
• OSTI ID: 1256633
• Report Number(s): PPPL-5153
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 3 Vol. 68; ISSN 1536-1055
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
disruptions
port plugs