Effect of Hydrogen on Thermal Creep Behaviour of Zr–2.5Nb Pressure Tube

Author(s):  
Vivek Patel ◽  
R. N. Singh ◽  
Avinash Gopalan
2002 ◽  
Vol 33 (4) ◽  
pp. 1103-1115 ◽  
Author(s):  
N. Christodoulou ◽  
C. K. Chow ◽  
P. A. Turner ◽  
C. N. Tomé ◽  
R. J. Klassen

Author(s):  
Brian W. Leitch ◽  
Nicolas Christodoulou ◽  
Ronald Rogge

The majority of the pressure-retaining components in the core of a CANDU power generation system are manufactured from zirconium. The horizontal fuel channel components and the fuel bundles that contain the natural uranium fuel are manufactured using various grades of zirconium. The fuel channel consists of two concentric tubes; an internally pressurized tube (Zr-2.5%Nb) that contains the fuel bundles (Zr-4) and the re-circulating heavy-water primary coolant, enclosed by a larger diameter calandria tube (Zircaloy) that separates the pressure tube from the heavy-water moderator. Re-fuelling and other fuel management operations can create surface defects in the tubes and fuel bundle sheathing. Stress analyses of these small notches may indicate that, under certain conditions, cracks can be formed at the root of these notches. These flaws are locations of stress concentration in the internally pressurized tube and can initiate a failure mechanism known as Delayed Hydride Cracking. The anisotropic material properties of these zirconium components adds an additional level of complexity in an analysis. However, the occurrences of these life-limiting events appear to be minimized mainly due to beneficial contributors such as stress relaxation around the scratches. One of the most likely reasons for this relaxation is thermal creep. Previously [1], the measurement and modeling of thermal creep relaxation under constant displacement was examined using 2-D finite element (FE) models. This paper extends both the measurement and modeling of the relaxing stress/strain field to the more demanding boundary condition of constant applied load. Neutron diffraction is used to determine the changing strain field around a single notched, axially orientated specimen loaded in tension. This specimen orientation and loading configuration is modeled in three dimensions using a hybrid explicit FE program [2] that contains materials subroutines that describe high stress creep specially developed to simulate the highly anisotropic creep response of pressure tube materials. Despite the difficulty of obtaining precise delineation of the moving strain field, a good agreement between the measurements and the 3-D FE creep results is achieved. Using the creep subroutines, the FE models are used to examine the creep response of a single notched, transversely orientated specimen loaded in tension in the hoop direction.


2006 ◽  
Vol 30 (12) ◽  
pp. 1526-1533
Author(s):  
Dong-Joon Oh ◽  
Young-Wha Ma ◽  
Kee-Bong Yoon ◽  
Young-Suk Kim
Keyword(s):  

2017 ◽  
Vol 698 ◽  
pp. 326-340 ◽  
Author(s):  
Kazi F. Ahmmed ◽  
Levente Balogh ◽  
Yasir Idrees ◽  
David Kerr ◽  
Mark R. Daymond

2018 ◽  
Vol 498 ◽  
pp. 20-32 ◽  
Author(s):  
Siddharth Suman ◽  
Mohd Kaleem Khan ◽  
Manabendra Pathak ◽  
R.N. Singh

Kerntechnik ◽  
2011 ◽  
Vol 76 (4) ◽  
pp. 237-243
Author(s):  
R. Kumar ◽  
A. J. Gaikwad ◽  
A. D. Contractor ◽  
A. Srivastava ◽  
H. G. Lele ◽  
...  

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