Texture and hydride orientation relationship of Zircaloy-4 fuel clad tube during its fabrication for pressurized heavy water reactors
- 1. Nuclear Fuel Complex, ECIL Post, Hyderabad 500 062 (India)
Description
Zircaloy-4 material is used for cladding tube in pressurized heavy water reactors (PHWRs) of 220 MWe and 540 MWe capacity in India. These tubes are fabricated by using various combinations of thermo-mechanical processes to achieve desired mechanical and corrosion properties. Cladding tube develops crystallographic texture during its fabrication, which has significant influence on its in-reactor performance. Due to radiolytic decomposition of water Zircaloy-4 picks-up hydrogen. This hydrogen in excess of its maximum solubility in reactor operating condition (∼300 deg. C), precipitates as zirconium hydrides causing embrittlement of cladding tube. Hydride orientation in the radial direction of the tube limits the service life and lowers the fuel burn-up in reactor. The orientation of the hydride primarily depends on texture developed during fabrication. A correlation between hydride orientation (Fn) with the texture in the tube during its fabrication has been developed using a second order polynomial. The present work is aimed at quantification and correlation of texture evolved in Zircaloy-4 cladding tube using Kearn's f-parameter during its fabrication process
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2008.08.035Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2008.08.035;
- PII
- S0022-3115(08)00479-0;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 383
- Journal Issue
- 1-2
- Journal Page Range
- p. 71-77
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- Processing, performance and phenomena
- Acronym
- International conference on advances in nuclear materials
- Dates
- 12-14 Dec 2006
- Place
- Mumbai (India)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40047162
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CLADDING; CORROSION; CRYSTALLOGRAPHY; EMBRITTLEMENT; NUCLEAR FUELS; ORIENTATION; PHWR TYPE REACTORS; PRECIPITATION; RADIOLYSIS; SERVICE LIFE; TEMPERATURE RANGE 0400-1000 K; TEXTURE; ZIRCALOY 4; ZIRCONIUM HYDRIDES
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DECOMPOSITION; DEPOSITION; ENERGY SOURCES; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDRIDES; HYDROGEN COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; LIFETIME; MATERIALS; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SURFACE COATING; TEMPERATURE RANGE; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.