Published 2004 | Version v1
Miscellaneous

Analysis of worn area characteristic in the fretting wear of nuclear fuel cladding

  • 1. KAERI, Taejon (Korea, Republic of)

Description

To evaluate the effect of spring shape on the fretting wear of nuclear fuel rod, sliding wear tests were performed using three kinds of space grid springs in room temperature air and water. With increasing slip amplitude, wear volume of each spring gradually increased. It is apparently shown that spring with convex shape had a relatively high wear resistance compared with concave shape springs. It is suggested that the ratio of the wear volume to the worn area can be suggested as an efficient and valid parameter to evaluate the wear resistibility of a fuel grid spring

Part of:
Proceedings of the KSME 2004 fall annual meeting

Additional details

Publishing Information

Publisher
KSME
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the KSME 2004 fall annual meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[6 p.]

Conference

Title
KSME 2004 fall annual meeting
Dates
3-5 Nov 2004
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36017364
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; FRETTING CORROSION; FUEL ASSEMBLIES; GRIDS; NUCLEAR FUELS; SHAPE; SPRINGS; WEAR; WEAR RESISTANCE
Descriptors DEC
CHEMICAL REACTIONS; CORROSION; DEPOSITION; ELECTRODES; ENERGY SOURCES; FUELS; MACHINE PARTS; MATERIALS; MECHANICAL PROPERTIES; REACTOR MATERIALS; SURFACE COATING

Optional Information

Notes
3 refs, 8 figs, 1 tab