Published October 2005
| Version v1
Book
Corrosion of zirconium alloy cladding materials
Creators
- 1. Atomic Fuels Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
The corrosion behaviour of zirconium alloy cladding materials in reactors is discussed
Additional details
Publishing Information
- Publisher
- Board of Research in Nuclear Sciences
- Imprint Place
- Mumbai (India)
- Imprint Title
- Cladding corrosion, embrittlement and pellet clad interaction: proceedings of theme meeting
- Imprint Pagination
- 179 p.
- Journal Page Range
- p. 17-25
Conference
- Title
- 2. high burnup issues in nuclear fuels
- Acronym
- HBINF-2005
- Dates
- 17 Oct 2005
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 37096359
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- BWR TYPE REACTORS; CLADDING; CORROSION; OXIDATION; REACTOR COOLING SYSTEMS; REACTOR CORES; ZIRCALOY 2; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-2; ALLOY-ZR98SN-4; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 9 figs.