Published 2004
| Version v1
Miscellaneous
The effect of lead on SCC of alloy 690
Creators
- 1. Kyushu Electric Power Corp., Inc., Research Laboratory, Fukuoka (Japan)
Description
no abstract available
Additional details
Publishing Information
- Imprint Title
- Symposium on water chemistry and corrosion in nuclear power plants in Asia 2003. Proceedings
- Imprint Pagination
- 334 p.
- Journal Page Range
- p. 313-316
Conference
- Title
- Symposium on water chemistry and corrosion in nuclear power plants in Asia 2003
- Dates
- 11-12 Nov 2003
- Place
- Fukuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35096578
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, No Abstract
- Descriptors DEI
- CRACKS; DEFECTS; HEAT TREATMENTS; INCONEL 690; LEAD; LEAD OXIDES; PH VALUE; RINGS; STRAINS; STRESS CORROSION; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; LEAD COMPOUNDS; MATERIALS; METALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; OXIDES; OXYGEN COMPOUNDS; TEMPERATURE RANGE; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 7 refs., 6 figs., 4 tabs.