Dynamic and Thermal Testing of a FW Panel Attachment System for the ITER Vessel

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F09%3A00160669" target="_blank" >RIV/68407700:21340/09:00160669 - isvavai.cz</a>
Alternative codes found
RIV/47718684:_____/09:#0000391
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Dynamic and Thermal Testing of a FW Panel Attachment System for the ITER Vessel
Original language description
The goal was to check the stiffness, strength limit, and fatigue behavior of the First Wall panel attachment system of key-keyway type for the blanket system of the fusion reactor ITER. The panel screwed to the shield was loaded alternatively by cyclic radial moment, poloidal force, or poloidal moment at room temperature. The stud bending stresses, stud pre-load relaxation, cyclic deformation, radial gap at the key-way and a plastic deformations were studied. Additional FE simulations were used for better interpretation of measurements. Thermal cycling led only to slight stud pre-load drop whereas the dynamic cycling itself did not cause an additional loss of the pre-load. The individual loads did not cause a loss of radial contact in the keyway or itsdamage even under a low stud's pre-load. A small radial gap in the key way was observed only under maximum poloidal moment with an extremely low stud pre-load.
Czech name
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Czech description
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Publication year
2009
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
Proceedings of the ASME Pressure Vessels and Piping Conference
ISBN
978-0-7918-3854-9
ISSN
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e-ISSN
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Number of pages
10
Pages from-to
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Publisher name
American Society Of Mechanical Engineers - ASME
Place of publication
New York
Event location
Praha
Event date
Jul 26, 2009
Type of event by nationality
EUR - Evropská akce
UT code for WoS article
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