Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals

The friction force between the contact surfaces of a reactor internal hold-down spring (HDS) and core barrel flanges can directly influence the axial stiffness of an HDS. However, friction coefficient cannot be obtained through theoretical analysis. This study performs a mathematical deduction of th...

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Veröffentlicht in:	Kerntechnik (1987) 2017-10, Vol.82 (5), p.579-585
Hauptverfasser:	Linjun, Xie, Guohong, Xue, Ming, Zhang
Format:	Artikel
Sprache:	eng
Online-Zugang:	Volltext
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