Title :
ITER divertor cassette and PFC attachment structural design
Author_Institution :
Boeing Co., St. Louis, MO, USA
Abstract :
High heat fluxes and high electromagnetic loads make for a challenging combination in the design of the ITER divertor cassette and plasma facing component (PFC) attachments. The cassette body must be able to handle high bending moments imposed by the electromagnetic (EM) forces in areas with cross sections that are reduced due to the coolant channel, vacuum port, gas box, shoe and PFC cut-outs. The ITER divertor cassette design incorporates removable, high heat flux components (PFCs) whose lives are shorter than the cassette body due to the more severe loading conditions. The PFC attachments must be designed to withstand the high EM and thermal loads and have limited constraint in order to minimize thermal stresses. The EM loads on the divertor cassette result in typical forces on the PFCs in the order of 1 MN and bending moments on the body of 1 MN-m. The forces used in the structural design represent a fast Vertical Displacement Event (VDE) with a 100 ms quench. In addition, thermal loads must also be considered in the design. The surface heat fluxes range from a nominal of 5 MW/m2 to a peak of 20 MW/m2 and are incident on the PFC surfaces. Volumetric heating also occurs, peaking at 10 W/cm3 in the PFCs and 0.5 W/cm3 in the body. These surface heat fluxes and volumetric heating result in differential temperatures and growth between the PFCs and cassette body. The attachment concepts must themselves be maintained within allowable temperatures, which limits their size and requires a certain proximity to coolant. The heat fluxes require the body to have frequent coolant channels to maintain temperature limits. These must be placed so they do not compromise the structural integrity of the cassette. Cassette body cross sections and PFC attachments must be designed to withstand these loads. General cassette design guidelines and cross sectional requirements have been examined for the body. A variety of attachment concepts have been examined for the different PFC locations and conditions. Dumbbell, keyhole, hat, L- and T-shaped attachments have been examined as well as a lug with a mandrel expanded hollow pin
Keywords :
Tokamak devices; fusion reactor design; thermal stresses; Dumbbell-shaped attachments; ITER divertor cassette; L-shaped attachments; PFC attachment structural design; PFC cut-outs; T-shaped attachments; coolant channel; coolant channels; electromagnetic forces; fast Vertical Displacement Event; gas box; hat-shaped attachments; high bending moments; high electromagnetic loads; high heat fluxes; keyhole-shaped attachments; lug; mandrel expanded hollow pin; plasma facing component; quench; removable high heat flux components; severe loading conditions; shoe; structural design; structural integrity; surface heat fluxes; thermal stresses; vacuum port; volumetric heating; Coolants; Electromagnetic forces; Footwear; Heating; Plasma temperature; Tensile stress; Thermal force; Thermal loading; Thermal quenching; Thermal stresses;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687062