MELTING AND FORMING OF SER FUEL RODS
Abstract
Sixty-one metal alloy reds were fabricated for the SNAP Experimental Reactor (SER), a compact nuclear power source. These rads were 1 in. in diameter by 10 in. long and consisted of an alloy containing 7 wt.% highly enriched uranium and 93 wt.% zinconium. Melting of the alloy was done by generally accepted consumable-arc meltiag techniques. Extrusion of alloy slugs into rods was carried out, unclad, at 850 deg F. Suitable controls were developed to insure uniformity of products and reproducibility of batches. The procedures developed for this application are considered adequate for future requirements. (auth)
- Authors:
- Publication Date:
- Research Org.:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- OSTI Identifier:
- 4130788
- Report Number(s):
- NAA-SR-4762
- NSA Number:
- NSA-15-000585
- DOE Contract Number:
- AT-11-1-GEN-8
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
- Subject:
- METALS, CERAMICS, AND OTHER MATERIALS; ALLOYS; CONTROL; ELECTRIC ARCS; ENRICHMENT; EXTRUSION; FUEL ELEMENTS; MELTING; RODS; STANDARDS; TEMPERATURE; URANIUM ALLOYS; ZIRCONIUM ALLOYS; NESDPS Office of Nuclear Energy Space and Defense Power Systems
Citation Formats
Drennan, P S. MELTING AND FORMING OF SER FUEL RODS. United States: N. p., 1960.
Web. doi:10.2172/4130788.
Drennan, P S. MELTING AND FORMING OF SER FUEL RODS. United States. https://doi.org/10.2172/4130788
Drennan, P S. Sat .
"MELTING AND FORMING OF SER FUEL RODS". United States. https://doi.org/10.2172/4130788. https://www.osti.gov/servlets/purl/4130788.
@article{osti_4130788,
title = {MELTING AND FORMING OF SER FUEL RODS},
author = {Drennan, P S},
abstractNote = {Sixty-one metal alloy reds were fabricated for the SNAP Experimental Reactor (SER), a compact nuclear power source. These rads were 1 in. in diameter by 10 in. long and consisted of an alloy containing 7 wt.% highly enriched uranium and 93 wt.% zinconium. Melting of the alloy was done by generally accepted consumable-arc meltiag techniques. Extrusion of alloy slugs into rods was carried out, unclad, at 850 deg F. Suitable controls were developed to insure uniformity of products and reproducibility of batches. The procedures developed for this application are considered adequate for future requirements. (auth)},
doi = {10.2172/4130788},
url = {https://www.osti.gov/biblio/4130788},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {10}
}
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