DocumentCode :
324994
Title :
Mechanical design considerations of a spherical torus volumetric neutron source
Author :
Sviatoslavsky, LN ; Cheng, E.T. ; Cerbone, R.J. ; Peng, Y.-K.M. ; Galambos, J.D. ; Strickler, D.J. ; Wang, X.R.
Author_Institution :
Wisconsin Univ., Madison, WI, USA
Volume :
1
fYear :
1997
fDate :
6-10 Oct 1997
Firstpage :
253
Abstract :
The mechanical design of a spherical torus based volumetric neutron source (ST VNS) is being studied under the support of a DOE-SBIR funding. A device capable of staged operation from a neutron wall loading of 0.5-5.0 MW/m2 has been scoped out, as the physics and engineering design assumptions are raised from modest to aggressive levels. Margins in the design are ensured since operation of the VNS will be adequate at a wall loading of 2 MW/m2. The device has a naturally diverted plasma with major radius of 1.07 m, a minor radius of 0.77 m for an aspect ratio of 1.4, an elongation of 3 and triangularity of 0.6. In the neutral beam driven version, the plasma current is 11.1 MA and the toroidal field at the plasma major radius is 2.13 T. The baseline fusion power is 151 MW giving an average neutron wall loading of 2 MW/m2 on the outboard side over an accessible area of over 15 m2 for blanket testing. The device utilizes a normal Cu conducting bell jar as the return leg of the toroidal field current, a concept developed at the Oak Ridge National Laboratory, The current is carried by an unshielded single-turn center post (CP) made of dispersion strengthened Cu which is cooled by water in a single pass from top to bottom. A special sliding electrical interface between the CP and the bed jar is provided on the upper end to allow for differential expansion and to isolate the CP from tensile and torsional forces from the bell jar. The ohmic heating in the CP is 153 MW at the start of operation and increases to 178 MW after 3 full power years of operation. Over this period the maximum Cu temperature does not exceed 160 C. This report primarily deals with the design of the CP, one of the most challenging issues of a low aspect ratio spherical torus. Maintenance approaches for the CP and the divertor assemblies have been determined and are addressed in the paper
Keywords :
fusion reactor design; fusion reactor ignition; fusion reactor operation; neutron sources; nuclear reactor maintenance; plasma beam injection heating; plasma ohmic heating; plasma toroidal confinement; 1.54 m; 11.1 MA; 151 MW; 153 MW; 178 MW; 2.13 T; 2.14 m; Cu; NBI heating; average neutron wall loading; baseline fusion power; differential expansion; divertor assemblies; engineering design assumptions; fusion reactors; maintenance; mechanical design; naturally diverted plasma; neutral beam driven version; neutron wall loading; ohmic heating; physics design assumptions; sliding electrical interface; spherical torus volumetric neutron source; staged operation; toroidal field current; unshielded single-turn center post; Design engineering; Heating; Laboratories; Leg; Neutrons; Particle beams; Physics; Plasma devices; Plasma temperature; Testing;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
Type :
conf
DOI :
10.1109/FUSION.1997.687031
Filename :
687031
Link To Document :
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