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The Irradiation of Aluminum Alloy-clad Thoria-urania Pellets

The Irradiation of Aluminum Alloy-clad Thoria-urania Pellets PDF Author: L. A. Neimark
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 42

Book Description
Specimens consisting of thorium oxide-uranium oxide pellets lead-bonded to extruded Al-1wt.% Ni alloy cladding were irradiated to maximum burnups of 33,200 MWd/T of oxide and to peak heat ratings. The specimens were BORAX-V fuel plates. The thorium oxide-uranium oxide solid solutions were formed by air-firing cold-pressed mixtures of thorium oxide and U3O8 to a final oxygen-to-metal atom ratio of about 2.05 to 1. Fuel compositions irradiated were 6.36, 12.7, and 25.6 wt.% UO2 in ThO2. Two specimen failures were attributed to fuel thermal expansion in areas of thin-walled cladding. The hyperstoichiometry of the fuel with respect to oxygen was believed to have caused a lower fuel thermal conductivity and abnormally large amounts of recrystallization, grain growth, and fission gas release. Fission gas release ranged from 4.6 to 82.3% of the theoretical gas generated.

The Irradiation of Aluminum Alloy-clad Thoria-urania Pellets

The Irradiation of Aluminum Alloy-clad Thoria-urania Pellets PDF Author: L. A. Neimark
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 42

Book Description
Specimens consisting of thorium oxide-uranium oxide pellets lead-bonded to extruded Al-1wt.% Ni alloy cladding were irradiated to maximum burnups of 33,200 MWd/T of oxide and to peak heat ratings. The specimens were BORAX-V fuel plates. The thorium oxide-uranium oxide solid solutions were formed by air-firing cold-pressed mixtures of thorium oxide and U3O8 to a final oxygen-to-metal atom ratio of about 2.05 to 1. Fuel compositions irradiated were 6.36, 12.7, and 25.6 wt.% UO2 in ThO2. Two specimen failures were attributed to fuel thermal expansion in areas of thin-walled cladding. The hyperstoichiometry of the fuel with respect to oxygen was believed to have caused a lower fuel thermal conductivity and abnormally large amounts of recrystallization, grain growth, and fission gas release. Fission gas release ranged from 4.6 to 82.3% of the theoretical gas generated.

Irradiation of an Aluminum Alloy-clad Ceramic Pellet-fueled Plate

Irradiation of an Aluminum Alloy-clad Ceramic Pellet-fueled Plate PDF Author: A. P. Gavin
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 50

Book Description
The specimen performed satisfactorily in spite of several factors which made conditions more severe than those expected to exist in a reactor fueled with this type of element.

Reports Received by Division of Technical Information Extension

Reports Received by Division of Technical Information Extension PDF Author: U.S. Atomic Energy Commission. Division of Technical Information
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 914

Book Description


Nuclear Science Abstracts

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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1202

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Category : Energy development
Languages : en
Pages : 378

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Category : Nuclear engineering
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Pages : 86

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Category : Ceramics
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Miscellaneous Publication - National Bureau of Standards

Miscellaneous Publication - National Bureau of Standards PDF Author: United States. National Bureau of Standards
Publisher:
ISBN:
Category : Weights and measures
Languages : en
Pages : 84

Book Description


Miscellaneous Publications

Miscellaneous Publications PDF Author:
Publisher:
ISBN:
Category : Weights and measures
Languages : en
Pages : 84

Book Description