Irradiation growth of zirconium alloy nuclear reactor structural components

1983 ◽  
Vol 4 (4) ◽  
pp. 195-216 ◽  
Author(s):  
D. O. Northwood ◽  
R. A. Herring
2020 ◽  
Author(s):  
Patrick Champlin ◽  
Christian Petrie ◽  
Annabelle Le Coq ◽  
Kurt Smith ◽  
Kory Linton

2006 ◽  
Vol 321-323 ◽  
pp. 1576-1579
Author(s):  
Yong Moo Cheong ◽  
Young Suk Kim

Zirconium alloys are used for many applications in nuclear components, such as the pressure tube material in a pressurized heavy water reactor, nuclear fuel cladding, etc. One of the problems during the operation of a nuclear reactor is the degradation of the zirconium alloys, which is due to an increase of the hydrogen content in the zirconium alloy. Therefore a non-destructive determination of the hydrogen concentration in zirconium alloy is one of the important issues that need to be addressed. The resonant ultrasound spectroscopy (RUS) technique is evaluated for a characterization of the hydrogen concentration in Zr-2.5Nb alloy. Referring to the terminal solid solubility for dissolution (TSSD) of Zr-2.5Nb alloy, the plot of the mechanical damping coefficient (Q-1) versus the temperature or the deviation of the resonant frequency for the temperature (df/dT) versus the temperature was correlated for the hydrogen concentration in Zr-2.5Nb alloy. It was found that the temperature at an abrupt change of the slope can be correlated with the hydrogen concentration of the Zr-2.5Nb alloy.


2000 ◽  
Vol 279 (2-3) ◽  
pp. 360-363 ◽  
Author(s):  
H.C González ◽  
A.M Fortis ◽  
G.D.H Coccoz

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