Studies in fusion reactor technology. Final report, September 1, 1974--August 31, 1977

Technical Report · Mon Aug 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/7086203· OSTI ID:7086203

Axtmann, R C; Perkins, H K

Two independent measurements of hydrogen permeation through stainless steel at driving pressures in the range from 10/sup -6/ to 1 Pa indicate that most extant predictions of tritium permeation through fusion reactors are probably overestimated grossly. A comprehensive analysis demonstrates that, given available structural materials, the prospects are negligible for the economic production of synthetic fuels via radiolytic reactions in fusion reactor systems.

• Research Organization: Princeton Univ., N.J. (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: EY-76-S-02-3028
• OSTI ID: 7086203
• Report Number(s): COO-3028-29; TRN: 77-020097
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DEUTERIUM
DIFFUSION
STAINLESS STEEL-304
PERMEABILITY
STAINLESS STEEL-304L
SYNTHETIC FUELS
PRODUCTION
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
FUELS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
NICKEL ALLOYS
NUCLEI
ODD-ODD NUCLEI
STABLE ISOTOPES
STAINLESS STEELS
STEELS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing