Published January 1981
| Version v1
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Fretting and wear of stainless and ferritic steels in LMFBR steam generators
- 1. UKAEA Risley Nuclear Power Development Labs.
Description
Steam generators for LMFBR's may be subject to both fretting wear as a result of flow-induced vibrations and to wear from larger amplitude sliding movements from thermal changes. Results of tests simulating the latter are given for stainless and ferritic steels. For the assessment of fretting wear damage, vibration assessments must be combined with data on specific wear rates. Test mechanisms used to study fretting in sodium covering impact, impact-slide and pure rubbing are described and results presented. (author)
Availability note (English)
MF available from INIS under the Report Number.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- ND-R--572(R)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 13662090
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ABRASION; CHROMIUM-MOLYBDENUM STEELS; FERRITIC STEELS; FRETTING CORROSION; LMFBR TYPE REACTORS; MECHANICAL VIBRATIONS; STAINLESS STEEL-304; STAINLESS STEEL-316; STEAM GENERATORS; TUBES; WEAR
- Descriptors DEC
- ALLOYS; BOILERS; BREEDER REACTORS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; REACTORS; STAINLESS STEELS; STEELS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS