PRODUCTION OF TRITIUM
Abstract
This invention relates to a process for the production of tritium by subjecting comminuted solid lithium fluoride containing the lithium isotope of atomic mass number 6 to neutron radiation in a self-sustaining neutronic reactor. The lithium fiuoride is heated to above 450 deg C. in an evacuated vacuum-tight container during radiation. Gaseous radiation products are withdrawn and passed through a palladium barrier to recover tritium. (AEC)
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4771424
- Patent Number(s):
- 3079317
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01B - NON-METALLIC ELEMENTS
- NSA Number:
- NSA-17-012356
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; BARRIERS; HEATING; IRRADIATION; ISOTOPE SEPARATION; LITHIUM 6; LITHIUM FLUORIDES; NEUTRON SOURCES; PALLADIUM; PRESSURE VESSELS; PRODUCTION; RECOVERY; SOLIDS; TRITIUM; VACUUM
Citation Formats
Jenks, G H, Shapiro, E M, Elliott, N, and Cannon, C V. PRODUCTION OF TRITIUM. United States: N. p., 1963.
Web.
Jenks, G H, Shapiro, E M, Elliott, N, & Cannon, C V. PRODUCTION OF TRITIUM. United States.
Jenks, G H, Shapiro, E M, Elliott, N, and Cannon, C V. Tue .
"PRODUCTION OF TRITIUM". United States.
@article{osti_4771424,
title = {PRODUCTION OF TRITIUM},
author = {Jenks, G H and Shapiro, E M and Elliott, N and Cannon, C V},
abstractNote = {This invention relates to a process for the production of tritium by subjecting comminuted solid lithium fluoride containing the lithium isotope of atomic mass number 6 to neutron radiation in a self-sustaining neutronic reactor. The lithium fiuoride is heated to above 450 deg C. in an evacuated vacuum-tight container during radiation. Gaseous radiation products are withdrawn and passed through a palladium barrier to recover tritium. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {2}
}
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