Tritium permeation and wall loading in the TFTR vacuum vessel

Technical Report · Mon May 01 04:00:00 EDT 1978

DOI:https://doi.org/10.2172/7079974· OSTI ID:7079974

Cecchi, J L

The problems of tritium permeation through and loading of the TFTR vacuum vessel wall structural components are considered. A general analytical solution to the time dependent diffusion equation which takes into account the boundary conditions arising from the tritium filling gas as well as the source function associated with implanted energetic charge exchange tritium is presented. Expressions are derived for two quantities of interest: (1) the total amount of tritium leaving the outer surface of a particular vessel component as a function of time, and (2) the amount retained as a function of time. These quantities are evaluated for specific TFTR operating scenarios and outgassing modes. The results are that permeation through the vessel is important only for the bellows during discharge cleaning if the wall temperature rises above approximately 150/sup 0/C. At 250/sup 0/C, after 72 hours of discharge cleaning 195 Ci would be lost.

• Research Organization: Princeton Univ., N.J. (USA). Plasma Physics Lab.
• DOE Contract Number: EY-76-C-02-3073
• OSTI ID: 7079974
• Report Number(s): PPPL-1422
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CLEANING
CORROSION RESISTANT ALLOYS
DIFFUSION
FIRST WALL
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
PERMEABILITY
POWER DENSITY
RADIOISOTOPES
STAINLESS STEELS
STEELS
TFTR REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
WALL LOADING
YEARS LIVING RADIOISOTOPES