Mechanical testing of PHWR components at different fabrication stages
Description
Zirconium alloys are extensively used for reactor structural and cladding components for PHWRs and BWRs due to their low neutron absorption cross-section, corrosion resistance to high temperature aqueous environments, adequate mechanical properties and resistance to radiation damage. The coolant tube fabrication route consists of a series of intermediate process steps. The working parameters of each process have a definite bearing on the final properties of these tubes. In order to ascertain the effect of these parameters, mechanical testing is carried out at intermediate stage of coolant tube fabrication. The mechanical properties of the products can be correlated with process parameters and reflect the quality of the product to a great extent. These properties at intermediate stages can serve as process controlling parameters. This paper discusses the correlation of mechanical properties of pressure tubes between the intermediate stage and final stage. The effect of process parameters like annealing temperature, honing, sand blasting pressure and eccentricity on the final mechanical properties was highlighted. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the theme meeting on modern developments and practices in mechanical testing of structural materials
- Imprint Pagination
- 289 p.
- Journal Page Range
- p. 1-13
Conference
- Title
- theme meeting on modern developments and practices in mechanical testing of structural materials
- Acronym
- MDPMT-2007
- Dates
- 10-11 Oct 2007
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 46060141
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; CALANDRIAS; CLADDING; PHWR TYPE REACTORS; REACTOR COOLING SYSTEMS; RESIDUAL STRESSES; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CONTAINERS; COOLING SYSTEMS; DEPOSITION; ENERGY SYSTEMS; HEAT TREATMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; STRESSES; SURFACE COATING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 2 refs., 9 figs., 6 tabs.