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Control Rod Drop Surveillance Using Two Friction Coefficients

Blázquez, J. ; Vallejo, I. ; García-Berrocal, A. ; Balbás, M.

Nuclear technology, 2011-11, Vol.176 (2), p.284-289 [Periódico revisado por pares]

La Grange Park, IL: Taylor & Francis

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Título:
Control Rod Drop Surveillance Using Two Friction Coefficients
Autor: Blázquez, J. ; Vallejo, I. ; García-Berrocal, A. ; Balbás, M.
Assuntos: Applied sciences ; Computational fluid dynamics ; Control rods ; Curvature ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fluid flow ; Friction ; Fuels ; Hydraulics ; Installations for energy generation and conversion: thermal and electrical energy ; Mathematical models ; Nuclear fuels ; Sliding
É parte de: Nuclear technology, 2011-11, Vol.176 (2), p.284-289
Notas: ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
Descrição: In the case of large burnup, a control rod (CR) guide tube in the pressurized water reactor of a commercial nuclear power plant might bend. As a consequence, a CR drop experiment may indicate an event of a CR partially inserted and whether the CR should be deemed inoperable. Early prevention of such an event can be achieved by measuring two friction coefficients: the hydraulic coefficient and the sliding coefficient. The hydraulic coefficient hardly changes, so that the curvature of the guide tube can only be detected thanks to a variation of the sliding coefficient. A simple model for the CR drop is established and validated with CR drop experiments. If t mx denotes the instant of CR maximum velocity, a linear relationship between (t mx ) -2 and the sliding coefficient is found.
Editor: La Grange Park, IL: Taylor & Francis
Idioma: Inglês

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Control Rod Drop Surveillance Using Two Friction Coefficients

Blázquez, J. ; Vallejo, I. ; García-Berrocal, A. ; Balbás, M.

La Grange Park, IL: Taylor & Francis

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