Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors

Author(s):  
VF Urbanic ◽  
BD Warr ◽  
A Manolescu ◽  
CK Chow ◽  
MW Shanahan
2010 ◽  
Vol 7 (7) ◽  
pp. 102979 ◽  
Author(s):  
H. M. Nordin ◽  
A. J. Elliot ◽  
S. G. Bergin ◽  
P. Barberis ◽  
S. W. Dean

2011 ◽  
Author(s):  
T. Sogawa ◽  
N. Matsunami ◽  
N. Ohno ◽  
M. Tokitani ◽  
S. Masuzaki ◽  
...  

Author(s):  
Cheng Liu ◽  
Douglas Scarth ◽  
Alain Douchant

Flaws found during in-service inspection of CANDU Zr-2.5Nb pressure tubes include fuel bundle scratches, debris fretting flaws, fuel bundle bearing pad fretting flaws, mechanical damage flaws and crevice corrosion marks. The CSA Standard N285.8 contains procedures and acceptance criteria for evaluation of the structural integrity of CANDU Zr-2.5Nb pressure tubes containing flaws. One of the requirements is to evaluate the flaws for fatigue crack initiation. There was a need to develop a statistical-based model of fatigue crack initiation at flaws for use in deterministic and probabilistic assessments of Zr-2.5Nb pressure tubes. A number of fatigue crack initiation experiments have been performed on notched specimens from irradiated and unirradiated Zr-2.5Nb pressure tube material with a range of hydrogen equivalent concentrations. These experiments were performed in an air environment and included temperature and load rise time as test parameters. The test data has been used to develop a statistical-based model of fatigue crack initiation at flaws that covers the effects of flaw root radius, load rise time and irradiation. This paper describes the development of the statistical-based model.


2013 ◽  
Vol 2 (1) ◽  
pp. 20120033
Author(s):  
R. N. Singh ◽  
A. K. Bind ◽  
J. B. Singh ◽  
J. K. Chakravartty ◽  
V. Thomas Paul ◽  
...  

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