Tritium permeation through Incoloy 800 oxidized in situ by water vapor
The in situ formation of oxide layers on the surfaces of heat exchangers in the steam system of a fusion power plant may be the most feasible way to control tritium release into the steam. Tritium permeabilities of Incoloy 800 have been determined while the downstream surface was oxidized by water vapor at 525, 660 and 720/sup 0/C. The in situ formation of oxide coatings on the Incoloy 800 surface has been observed to reduce tritium permeabilities by factors of 30 to 700 depending on conditions. The effects of the in situ formed oxide coatings to impede tritium permeation are dependent on the chemical and physical compositions of the oxides, and the compositions of the oxides have been observed to depend on the history of the material.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6728907
- Report Number(s):
- CONF-780508-12
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700204 -- Fusion Power Plant Technology-- Cooling Systems
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHALCOGENIDES
CHROMIUM ALLOYS
COATINGS
DIFFUSION
HEAT EXCHANGERS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
INCOLOY 800
INCOLOY ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PERMEABILITY
RADIOISOTOPES
STEAM
STEAM TURBINES
THERMODYNAMIC CYCLES
THERMONUCLEAR REACTORS
TRITIUM
TURBINES
TURBOMACHINERY
YEARS LIVING RADIOISOTOPES