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Crucible Materials to Contain Molten Uranium.

Y2084

Publication Date	1977
Personal Author	Condon, J. B.; Holcombe, C. E.
Page Count	76
Abstract	A determination has been made of the interactions of molten uranium with possible containment materials. Containment materials included pure, free-standing ceramics and metal oxides supported on graphite. Consideration was also given to the interaction of graphite with twelve metal oxides and five mixed oxides. Free-standing ceramics included seven metallic borides, eleven carbides, seven nitrides, three oxides, and four sulfides. Solubilities of these materials in molten uranium at 1673 K were determined. Yttria, supported on graphite, appeared to be the best choice of container material for melting uranium; however, other options are available. (ERA citation 03:004328)
Keywords	Ceramics Crucibles Uranium Compatibility Graphite Materials Melting Oxides Solubility Yttrium oxides ERDA/360101 ERDA/360204 Borides Carbides Nitrides Sulfides
Source Agency	US Energy Research and Development Administration
NTIS Subject Category	71D - Ceramics, Refractories, & Glass 77I - Reactor Fuels & Fuel Processing
Corporate Authors	Oak Ridge Y-12 Plant, Tenn.; Energy Research and Development Administration.
Document Type	Technical Report
NTIS Issue Number	197806
Contract Number	W-7405-ENG-26

Crucible Materials to Contain Molten Uranium.

Crucible Materials to Contain Molten Uranium.
Y2084

Publication Date	1977
Personal Author	Condon, J. B.; Holcombe, C. E.
Page Count	76
Abstract	A determination has been made of the interactions of molten uranium with possible containment materials. Containment materials included pure, free-standing ceramics and metal oxides supported on graphite. Consideration was also given to the interaction of graphite with twelve metal oxides and five mixed oxides. Free-standing ceramics included seven metallic borides, eleven carbides, seven nitrides, three oxides, and four sulfides. Solubilities of these materials in molten uranium at 1673 K were determined. Yttria, supported on graphite, appeared to be the best choice of container material for melting uranium; however, other options are available. (ERA citation 03:004328)
Keywords	Ceramics Crucibles Uranium Compatibility Graphite Materials Melting Oxides Solubility Yttrium oxides ERDA/360101 ERDA/360204 Borides Carbides Nitrides Sulfides
Source Agency	US Energy Research and Development Administration
NTIS Subject Category	71D - Ceramics, Refractories, & Glass 77I - Reactor Fuels & Fuel Processing
Corporate Authors	Oak Ridge Y-12 Plant, Tenn.; Energy Research and Development Administration.
Document Type	Technical Report
NTIS Issue Number	197806
Contract Number	W-7405-ENG-26