Tritium permeation scoping test
The efficacy of a permeation experimental design employing dual helium flow loops, flow-through ion chamber detectors and Zr/Al alloy getter pumps was investigated through a series of permeation experiments on as-received 316 stainless steel at 773 K. Tritium partial pressures of 3 to 6 x 10/sup -4/ Pa (6 to 13 mCi/m/sup 3/) were used to simulate the expected first wall background conditions as well as those planned for the EG and G fission reactor studies. The results and observations of the study demonstrated that oxidation of tritium must be prevented if a circulation loop, tritium detection technique is to be successful in an in-reactor assembly. Possible modifications to the in-reactor experimental design are presented.
- Research Organization:
- Monsanto Research Corp., Miamisburg, OH (USA). Mound
- DOE Contract Number:
- AC04-76DP00053
- OSTI ID:
- 6629324
- Report Number(s):
- MLM-3029; ON: DE83003224
- Country of Publication:
- United States
- Language:
- English
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ALLOYS
ALUMINIUM ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DIFFUSION
GETTERS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
PERMEABILITY
RADIOISOTOPES
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES
ZIRCONIUM ALLOYS