Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants: Fid-Bau Portal

Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants

Park, C. Y. / Lee, J. K.

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Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants

Park, C. Y. / Lee, J. K.

Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants

Park, C. Y. / Lee, J. K.

Zugriff

Zugriff über TIB

Verfügbarkeit in meiner Bibliothek prüfen

Bestellung bei Subito €

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Ähnliche Titel

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Titel:

Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants

Beteiligte:

Park, C. Y. (Autor:in) / Lee, J. K. (Autor:in) / Lee, S.-B. / Kim, Y.-J.

Erschienen in:

Experimental Mechanics in Nano and Biotechnology ; 1251-1254

KEY ENGINEERING MATERIALS ; 326/328

Erscheinungsdatum:

01.01.2006

Format / Umfang:

4 pages

ISSN:

1013-9826

Medientyp:

Aufsatz (Zeitschrift)

Format:

Sprache:

Englisch

Klassifikation:

DDC: 620.11

Park, D. K. / Woo, S. W. / Chung, I. S. et al. | British Library Online Contents | 2007

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Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants

Park, C. Y. / Lee, Y. S. / Boo, M. H. | British Library Online Contents | 2005

Experimental investigation of long-term fretting wear of multi-span steam generator tubes with U-bend sections

Attia, M.H. / Magel, E. | British Library Online Contents | 1999

Wear Transitions of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions

Jeong, S. H. / Park, J. M. / Lee, J. H. et al. | British Library Online Contents | 2006

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