Performance of ceramic breeder materials in the SIBELIUS experiment
Technical Report
·
OSTI ID:47767
- Argonne National Lab., IL (United States)
- Pacific Northwest Labs., Richland, WA (United States)
Lithium containing ceramics are among the leading candidates for use as tritium breeding materials in a fusion reactor. An issue affecting both the safety and economics of the reactor is the tritium inventory. The SIBELIUS experiment was designed to examine material compatibility between different components of a breeder blanket and to examine the tritium inventory in the components of the blanket. The tritium inventory in each of the ceramics was determined by measurements at end of life and were found to be quite low and in agreement with those determined in tests with no beryllium present. The inventory increased in the order lithium zirconate < lithium oxide < lithium orthosilicate < lithium aluminate with the inventory in the zirconate less than 0.03 wppm at 550{degrees}C.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- OSTI ID:
- 47767
- Report Number(s):
- DOE/ER--0313/16; ON: DE95003404
- Country of Publication:
- United States
- Language:
- English
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