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Sintering of oxide nuclear fuel: Plastic flow mechanism

Baranov, V.G. ; Devyatko, Yu.N. ; Tenishev, A.V. ; Khlunov, A.V. ; Khomyakov, O.V.

Journal of nuclear materials, 2013-01, Vol.432 (1-3), p.52-56 [Periódico revisado por pares]

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Título:
Sintering of oxide nuclear fuel: Plastic flow mechanism
Autor: Baranov, V.G. ; Devyatko, Yu.N. ; Tenishev, A.V. ; Khlunov, A.V. ; Khomyakov, O.V.
Assuntos: Capillarity ; Fuels ; Mathematical models ; Nuclear fuels ; Oxides ; Plastic flow ; Residual stress ; Sintering
É parte de: Journal of nuclear materials, 2013-01, Vol.432 (1-3), p.52-56
Notas: ObjectType-Article-1
SourceType-Scholarly Journals-1
ObjectType-Feature-2
content type line 23
Descrição: ► The model of oxide nuclear fuel sintering is constructed. ► The viscous flow of matter under internal stress and capillary forces is considered. ► The plastic flow mechanism allows describing an intermediate stage of sintering. ► We have calculated the sintering curves for oxide nuclear fuel. A theoretical approach to solving the sintering problem of nuclear oxide fuels is described. We are proposing a new physical sintering model: the main mechanism for oxide nuclear shrinkage is the plastic flow of the matter under internal stress and capillary forces.
Editor: Elsevier B.V
Idioma: Inglês

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