Accession Number DE2013-1022039
Title Mechanical Design Considerations of a Spherical Torus Volumetric Neutron Sources.
Publication Date 2012
Media Count 4p
Personal Author D. J. Strickler E. T. Cheng I. N. Sviatoslavsky J. D. Galambos R. J. Cerbone X. R. Wang Y. K. M. Peng
Abstract The mechanical design of a spherical torus based volumetric neutron source (ST VNS) is being studied under the support of a DOE-SIBIR 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 nleutron wall loading of 2MW/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 bell jar iis 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 sipherical torus. Maintenance approaches for the CP and the divertor assemblies have been determined and are addressed in the paper.
Keywords Aspect ratio
Beams
Design
Dispersions
Divertors
Electric currents
Heating
Interfaces
Maintenance
Neutron sources
Oak Ridge National Laboratory
Plasma
Tokomak devices
Wall loading
Water

 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77A - Thermonuclear Fusion Devices
46G - Plasma Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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