Stress-rupture behaviour of zirconium-2.5 niobium pressure tube alloy of 500 MWe PHWR
- 1. Bhabha Atomic Research Centre, Bombay (India). Metallurgy Div.
- 2. National Metallurgical Lab., Jamshedpur (India)
Description
Stress-ruptures tests at temperatures 300-450 C and stresses 100-480 MPa on specimens machined from a Zr-2.5% Nb pressure tube, are reported. Rupture stress and rupture ductility (pct. elongation) were analysed by Larsen-Miller parameter. It was observed that the calculated rupture ductility and rupture stress for 105 hours at 300 C were 29 percent and 340 MPa which satisfies the stress criteria for pressure tube design. Further it was noted that at a given temperature, the rupture time obeyed a power-law stress dependency, analogous to the relationship between minimum creep rate and stress and the ductility parameter defined as the product of minimum creep rate and rupture time depended on stress exponent. Based on these observations, an attempt has been made to explain the micro-mechanism of fracture phenomenon. (author). 7 refs., 8 figs., 2 tabs
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre.
- Imprint Place
- Bombay (India)
- Imprint Title
- Proceedings [of the] symposium on zirconium alloys for reactor components
- Imprint Pagination
- 738 p.
- Journal Page Range
- p. 257-271.
Conference
- Title
- symposium on zirconium alloys for reactor components.
- Acronym
- ZARC-91
- Dates
- 12-13 Dec 1991.
- Place
- Bombay (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 24066102
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLD WORKING; CREEP; DUCTILITY; ELONGATION; FRACTURES; GRAIN BOUNDARIES; NIOBIUM ALLOYS; PHWR TYPE REACTORS; PRESSURE TUBES; RUPTURES; STRAIN RATE; STRESSES; TRANSMISSION ELECTRON MICROSCO; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; CRYSTAL STRUCTURE; DEFORMATION; ELECTRON MICROSCOPY; FABRICATION; FAILURES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS WORKING; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; REACTORS; TENSILE PROPERTIES; TUBES; ZIRCONIUM ALLOYS