Published September 1985 | Version v1
Journal article

Tritium control in helium-cooled blankets

  • 1. GA Technologies Inc., San Diego, CA

Description

As a part of the Blanket Comparison and Selection Study (BCSS), GA Technologies was responsible for the design of helium-cooled, solidand liquid-metal breeder blankets. Conceptual blanket designs were developed, including the consideration of the generation, transport, and extraction of tritium. Evaluations were made of the inventory and leakage of tritium for helium-cooled Li2O and LiA102 and liquid lithium breeder blankets for tokamak and tandem mirror reactors. To facilitate the evaluation, a solid breeder tritium code TRIT4 was developed

Additional details

Publishing Information

Journal Title
Fusion Technol.
Journal Volume
8
Journal Issue
2
Series
Fusion Technol.
Journal Page Range
2133-2142
ISSN
0748-1896
CODEN
FUSTE

Conference

Title
2. national topical meeting on tritium technology in fission, fusion and isotopic applications.
Dates
30 Apr - 2 May 1985.
Place
Dayton, OH (USA).

Optional Information

Secondary number(s)
CONF-850405--.