Published May 1992 | Version v1
Book

Preliminary design of a solid particulate cooled blanket for the steady state tokamak reactor (SSTR)

  • 1. Kawasaki Heavy Industries, Ltd., Tokyo (Japan)
  • 2. Kyushu Univ., Fukuoka-ken (Japan)
  • 3. Japan Atomic Energy Research Inst., Ibaraki-ken (Japan)

Description

This paper describes the preliminary design of the steady state tokamak reactor (SSTR) blanket cooled by a mixture of helium gas and fine solid particles. Light yet highly heat resistant material, titanium aluminide (TiAl), is used as structural material. Thickness of tritium breeding blanket using lithiated ceramics and beryllium neutron multiplier is minimized and high-temperature and non-breeding shield blanket is installed to enhance blanket energy multiplication. It is found that TiAl is advantageous in radioactive waste management because the contact dose rate of TiAl first wall attenuates rapidly. The gas-particulate mixture coolant lowers the helium pressure to 5 MPa and reduces the volumetric flow rate when compared to a pure helium-cooled blanket. The net thermal efficiency larger than 40 % can be achieved with the outlet coolant temperature of 700C

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
Tenth topical meeting on the technology of fusion energy: Proceedings
Imprint Pagination
470 p.
Journal Page Range
p. 1744-1748.

Conference

Title
10. topical meeting on technology of fusion energy.
Dates
7-12 Jun 1992.
Place
Boston, MA (United States).