Actions for Examination of LiAlO
Examination of LiAlO/sub 2/ coproduct targets irradiated as PT-NR-57. Final report
- Author
- Weber, J. W.
- Published
- United States : [publisher not identified], 1966.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1966. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Summary
- Thirty-three Zr-2 canned coproduct targets of LiAlO/sub 2/ (lithium aluminate) were irradiated in N-reactor under production test PT-NR-57. These targets were irradiated to provide material for evaluation of a process for extracting tritium from lithium bearing ceramics and to evaluate the in-reactor performance of lithium bearing ceramic target elements fabricated by several processes. Each Zr-2 canned target, 1.250 in. ID x 25 in. long with either a 0.030 or 0.095 in. thick wall, contained two aluminum canned ceramic cores. The cores ultimately irradiated in this test were fabricated from lithium aluminate powder by one of the following processes: (1) Pressing and sintering to form pellets 1.12 in. diameter by approximately 2 /sup 1///sub 2/ in. long. (2) Bulk sintering, crushing, and vibratory compaction in aluminum tubes. (3) Direct encapsulation in aluminum by high energy techniques. The SZr-2 and aluminum can components of the targets showed no unusual features and appeared to perform their functions satisfactorily. Bulging of the aluminum end caps on two aluminum canned targets was caused by internal gas pressure but examination did not show any compromise of the can integrity. Gas release data was obtained by drilling into the aluminum cans of several elements. Measurement of the released gas volume and analysis of the released gases revealed that increasing the bulk density of the ceramic cores reduced the amount of gases released into the aluminum cans. Examination of the ceramic cores revealed no visible change in them as a result of irradiation. Other than the differences in the gas released from the cores there was no essential difference in the irradiation performance of the cores fabricated by the three techniques.
- Report Numbers
- BNWL-CC-945
- Other Subject(s)
- 060100 - fusion fuels- sources- (-1987).
- 36 materials science
- 360106 - metals & alloys- radiation effects
- 360605 - materials- radiation effects
- 38 radiation chemistry, radiochemistry, and nuclear chemistry
- 400703 - radiochemistry & nuclear chemistry- radioisotope production
- 70 plasma physics and fusion technology
- Alkali metal compounds
- Alloys
- Aluminates
- Aluminium compounds
- Aluminium
- Baryons
- Canning
- Ceramics
- Chromium additions
- Chromium alloys
- Elementary particles
- Elements
- Enriched uranium reactors
- Fabrication
- Fermions
- Graphite moderated reactors
- Hadrons
- Iron additions
- Iron alloys
- Lithium compounds
- Lwgr type reactors
- Materials working
- Metals
- N-reactor
- Neutrons
- Nucleons
- Oxygen compounds
- Physical radiation effects
- Pile neutrons
- Plutonium production reactors
- Power reactors
- Production reactors
- Radiation effects
- Reactors
- Recovery
- Targets
- Tin alloys
- Tritium recovery
- Water cooled reactors
- Zircaloy 2.
- Zircaloy
- Zirconium alloys
- Zirconium base alloys
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(45-1)-1830
OSTI Identifier 7346635
Research organization: Battelle Pacific Northwest Labs., Richland, Wash. (USA).
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