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Title: Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor

Abstract

Considerable technology has developed for production of tritium in metallic target systems. At normal N-Reactor temperatures ({approximately} 300{degrees}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{degrees}C. At the same time, gas retention at irradiation temperatures ({approximately}300{degrees}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.

Authors:
Publication Date:
Research Org.:
Battelle-Northwest, Richland, WA (United States). Pacific Northwest Lab.
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10124509
Report Number(s):
BNWL-CC-337-Del.
ON: DE94006963
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 3 Nov 1965
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; TRITIUM; PRODUCTION; N-REACTOR; LITHIUM SILICATES; LITHIUM ALLOYS; ALUMINIUM ALLOYS; IRRADIATION; EMISSION; TARGETS; HANFORD PRODUCTION REACTORS; EXTRACTION; FISSION PRODUCT RELEASE; IMPURITIES; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS

Citation Formats

Johnson, Jr, A B. Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor. United States: N. p., 1965. Web. doi:10.2172/10124509.
Johnson, Jr, A B. Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor. United States. https://doi.org/10.2172/10124509
Johnson, Jr, A B. Wed . "Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor". United States. https://doi.org/10.2172/10124509. https://www.osti.gov/servlets/purl/10124509.
@article{osti_10124509,
title = {Tritium release from lithium silicate and lithium aluminate, in-reactor and out-of-reactor},
author = {Johnson, Jr, A B},
abstractNote = {Considerable technology has developed for production of tritium in metallic target systems. At normal N-Reactor temperatures ({approximately} 300{degrees}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{degrees}C. At the same time, gas retention at irradiation temperatures ({approximately}300{degrees}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.},
doi = {10.2172/10124509},
url = {https://www.osti.gov/biblio/10124509}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1965},
month = {11}
}