Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1965. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 49 pages : digital, PDF file
- Additional Creators:
- Battelle Memorial Institute, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Considerable technology has developed for production of tritium in metallic target systems. At normal N-Reactor temperatures (∼ 300°C), aluminum-lithium alloys appear to offer a satisfactory system for tritium production. However, reactor safety requirements have generated interest in a target system which will hold the lithium in place at temperatures to 1200°C. At the same time, gas retention at irradiation temperatures (∼300°C) must be acceptable, and extraction of the product must be practical. To determine in-reactor gas release characteristics of the silicate and aluminate materials, targets were irradiated in quartz and aluminum capsules. Following irradiation, the gas (condensible and noncondensible fractions) released in-reactor was recovered by drilling the capsules. Subsequently, the targets were recovered and heated in a laboratory vacuum system to investigate characteristics of tritium and helium evolution as a function of temperature. The experimental procedures are discussed briefly, with details in the Appendix. The results of the study are discussed in terms of in-reactor release and later in terms of laboratory extractions.
- Published through SciTech Connect., 11/03/1965., "bnwl-cc--337-del.", "DE94006963", and Johnson, A.B. Jr.
- Type of Report and Period Covered Note:
- Topical; 11/01/1965 - 11/01/1965
- Funding Information:
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