Heavy Ion Irradiation Effects in Zr Excel Alloy Pressure Tube Material
36th Annual CNS-CNA Student Conference - 2012 June 12


Presented at:
36th Annual CNS-CNA Student Conference
2012 June 12
Location:
Saskatoon, Canada
Session Title:
CNS/CNA Student Conference 2012

Authors:
Y Idrees (Queen's University, Kingston )
Z Yao (Queen's University, Kingston )
M Sattari (Queen's University, Kingston )
M.R Daymond (Queen's University, Kingston )
  

Abstract

Zirconium Excel alloy (Zr-3.5wt.%Sn-0.8%Nb-0.8%Mo) is the candidate material for pressure tubes in the Generation-IV CANDU® Super Critical Water-cooled Reactor (SCWR) design. Changes in microstructure induced by neutron irradiation are known to have important consequences on the in-reactor deformation behavior. The in-situ ion irradiation technique has been employed to elucidate the irradiation damage in dual phase Zr-excel alloy (~70% hcp alpha and ~30% bcc beta). 1 MeV Kr ion irradiation experiments were conducted at different temperatures ranging from 100oC-400oC. Damage microstructures have been characterized by Transmission Electron Microscopy in both the alpha and beta phases at different temperatures after a maximum dose of 10 dpa. Several new observations including irradiation induced omega (?) phase precipitation have been reported. The ?/? orientation relationship was determined by the detailed analysis of selected area diffraction patterns. In-situ irradiation provided an opportunity to observe the nucleation and growth of basal plane c-component loops. It has been shown that under Kr ion irradiation the c-loops start to nucleate and grow above a threshold dose, as has been observed for neutron irradiation. Furthermore, the role of temperature, material composition and pre-irradiation microstructure has been discussed in detail.

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