Microstructural and hydriding studies of zirconium based materials for thermal reactor applications
- 1. Materials Science Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
The Zircaloy-2, Zircaloy-4 and Zr-2.5 Nb alloys, used as fuel cladding and other structural components, such as Calandria Tubes and Pressure Tubes, has shown satisfactory performance in pressurised heavy water reactors (PHWR's). However, there is always demand and scope for the better and improved performance of cladding and structural components which requires modification of process flow sheet and development of newer alloys e.g. PHWR reactors designed for higher operating temperature than the current PHWR operating temperature. There is also thrust for development of cladding material with better corrosion and mechanical properties suitable for higher and extended burn up applications. The mechanical properties, irradiation behaviour performance of the material is primarily influenced by the microstructural features such as constituent phases, their morphology, shape, size and size distribution of the precipitates, nature of defects etc. Therefore, tailoring of microstructure and study of the structure-property relationship is very important. The chemistry of the alloy and thermo-mechanical- treatments are manipulated for obtaining microstructure to obtain the desired performance. In the present study, a series of binary, ternary and quaternary alloys have been prepared. The basic phase transformation mechanisms and the microstructure evolution in these alloys after different heat treatments have been studied using optical scanning and transmission electron microscope. Some of the important results obtained will be presented. Hydriding is most important corrosion problem in the zirconium cladding alloys. The mechanism of hydride formation and their crystallographic and microstructural aspects will be presented in detail for relevant zirconium alloys. Zirconium alloys being crystallographically, asymmetric it shows deformation and annealing texture. Result of the studies on evolution of bulk and micro texture during deformation and hydriding will be highlighted. (author)
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. 55-59
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
- 37096363
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALANDRIAS; CLADDING; MICROSTRUCTURE; PHASE TRANSFORMATIONS; PHWR TYPE REACTORS; PRESSURE TUBES; ZIRCALOY 2; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-2; ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CONTAINERS; CORROSION RESISTANT ALLOYS; DEPOSITION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; REACTORS; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 19 figs.