DocumentCode :
2723800
Title :
Conceptual design of the tokamak radiation shielding for the Tokamak Physics Experiment (TPX)
Author :
Cole, M.J. ; Nelson, B.E. ; Fogarty, P.J. ; Jones, G.H. ; Goranson, P.L. ; Gohar, Y. ; Liew, S.L.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
Volume :
2
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
727
Abstract :
The tokamak radiation shielding includes the neutron and gamma shielding around the torus and penetrations required to (1) limit activation of components outside the shield to levels that permit hands-on maintenance and (2) limit the nuclear heating of the superconducting coils and cold structure. The primary design drivers are space, the 350°C bakeout temperature, and cost; therefore, different shield materials were used for different shield components and locations. The shielding is divided into three areas: (1) torus shielding around the vacuum vessel, (2) duct shielding around the vacuum pumping ducts and vertical diagnostic ducts, and (3) penetration shielding in and around the radial ports. The major shield components include water between the walls of the vacuum vessel, lead monosilicate/boron carbide tiles that are attached to the exterior of the vacuum vessel, shield plugs that fill the openings of the large radial ports, and polyethylene/lead/boron shield blocks for duct shielding. A description of the shielding configuration and the performance and operational requirements will be discussed
Keywords :
Tokamak devices; fusion reactor design; fusion reactor operation; fusion reactors; nuclear reactor maintenance; shielding; superconducting coils; vacuum pumps; 350 C; B4C; H2O; PbSiO; TPX; Tokamak Physics Experiment; bakeout temperature; cold structure; components activation limitation; conceptual design; duct shielding; fusion reactor; gamma shielding; hands-on maintenance; neutron shielding; nuclear heating; operational requirements; penetration shielding; primary design drivers; radial ports; superconducting coils; torus shielding; vacuum pumping ducts; vacuum vessel; vertical diagnostic ducts; water; Boron; Costs; Ducts; Heating; Neutrons; Superconducting coils; Superconducting materials; Temperature; Tiles; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518431
Filename :
518431
Link To Document :
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