Hydrogen Transport in the Oxide and Hydrogen Pickup by the Metal During Out- and In-Reactor Corrosion of Zr-2.5Nb Pressure Tube Material

2008 ◽  
pp. 853-853-24 ◽  
Author(s):  
N Ramasubramanian ◽  
V Perovic ◽  
M Leger
Keyword(s):  
Pressure Tube ◽  
Hydrogen Transport ◽  
Tube Material ◽  
Hydrogen Pickup

Variations in nanomechanical properties of back-end Zr–2.5Nb pressure tube material

2013 ◽  
Vol 442 (1-3) ◽  
pp. 116-123 ◽  
Author(s):  
Matthew Gallaugher ◽  
Daniel Peykov ◽  
Nicolas Brodusch ◽  
Richard R. Chromik ◽  
Lisa Rodrigue ◽  
...  
Keyword(s):  
Pressure Tube ◽  
Tube Material ◽  
Nanomechanical Properties

Engineering Relation for Dependence of Threshold Stress Intensity Factor for Delayed Hydride Cracking on Crack Orientation

2008 ◽  
Author(s):  
Douglas A. Scarth ◽  
Gordon K. Shek ◽  
Steven X. Xu
Keyword(s):  
Stress Intensity Factor ◽  
Stress Intensity ◽  
Intensity Factor ◽  
Threshold Stress ◽  
Pressure Tube ◽  
Threshold Stress Intensity ◽  
Tube Material ◽  
Fuel Bundle ◽  
Threshold Stress Intensity Factor ◽  
Cold Worked

Delayed Hydride Cracking (DHC) in cold-worked Zr-2.5 Nb pressure tubes is of interest to the CANDU industry in the context of the potential to initiate DHC at an in-service flaw. Examples of in-service flaws are fuel bundle scratches, crevice corrosion marks, fuel bundle bearing pad fretting flaws and debris fretting flaws. To date, experience with fretting flaws has been favourable, and crack growth from an in-service fretting flaw has not been detected. However, postulated DHC growth from these flaws can result in severe restrictions on the allowable number of reactor Heatup/Cooldown cycles prior to re-inspection of the flaw, and it is important to reduce any unnecessary conservatism in the evaluation of DHC from the flaw. One method to reduce conservatism is to take credit for the increase in the isothermal threshold stress intensity factor for DHC initiation at a crack, KIH, as the flaw orientation changes from an axial flaw to a circumferential flaw in the pressure tube. This increase in KIH is due to the texture of the pressure tube material. An engineering relation that provides the value of KIH as a function of the orientation of the flaw relative to the axial direction in the pressure tube has been developed as described in this paper. The engineering relation for KIH has been validated against results from DHC initiation experiments on unirradiated cold-worked Zr-2.5 Nb pressure tube material.

Analysis of steady-state thermal creep of Zr-2.5Nb pressure tube material

2002 ◽  
Vol 33 (4) ◽  
pp. 1103-1115 ◽  
Author(s):  
N. Christodoulou ◽  
C. K. Chow ◽  
P. A. Turner ◽  
C. N. Tomé ◽  
R. J. Klassen
Keyword(s):  
Steady State ◽  
Thermal Creep ◽  
Pressure Tube ◽  
Tube Material

A Probabilistic Integrity Assessment of Flaw in Zirconium Alloy Pressure Tube Considering Delayed Hydride Cracking

2003 ◽  
Vol 17 (08n09) ◽  
pp. 1587-1593 ◽  
Author(s):  
Sang Log Kwak ◽  
Joon Seong Lee ◽  
Young Jin Kim ◽  
Youn Won Park
Keyword(s):  
Probabilistic Analysis ◽  
Nuclear Reactor ◽  
Failure Criteria ◽  
Pressure Tube ◽  
Initial Surface ◽  
Tube Material ◽  
Integrity Assessment ◽  
Pressure Tubes ◽  
Delayed Hydride Cracking ◽  
Hydride Cracking

In the CANDU nuclear reactor, pressure tubes of cold-worked Zr-2.5Nb material are used in the reactor core to contain the nuclear fuel bundles and heavy water coolant. Pressure tubes are major component of nuclear reactor, but only selected samples are periodically examined due to numerous numbers of tubes. Pressure tube material gradually pick up deuterium, as such are susceptible to a crack initiation and propagation process called delayed hydride cracking (DHC), which is the characteristic of pressure tube integrity evaluation. If cracks are not detected, such a cracking mechanism could lead to unstable rupture of the pressure tube. Up to this time, integrity evaluations are performed using conventional deterministic approaches. So it is expected that the results obtained are too conservative to perform a rational evaluation of lifetime. In this respect, a probabilistic safety assessment method is more appropriate for the assessment of overall pressure tube safety. This paper describes failure criteria for probabilistic analysis and fracture mechanics analyses of the pressure tubes in consideration of DHC. Major input parameters such as initial hydrogen concentration, the depth and aspect ratio of an initial surface crack, DHC velocity and fracture toughness are considered as probabilistic variables. Failure assessment diagram of pressure tube material is proposed and applied in the probabilistic analysis. In all the analyses, failure probabilities are calculated using the Monte Carlo simulation. As a result of analysis, conservatism of deterministic failure criteria is showed.

Characterization of diamond-like carbon films deposited on Zr-2.5Nb pressure tube material by excimer laser

1997 ◽  
Vol 32 (9) ◽  
pp. 1253-1260
Author(s):  
K.F. Amouzouvi ◽  
L.J. Clegg ◽  
C. Möβner ◽  
H. Tran ◽  
P. Grant ◽  
...  
Keyword(s):  
Excimer Laser ◽  
Carbon Films ◽  
Pressure Tube ◽  
Diamond Like Carbon ◽  
Tube Material

Microstructural and Textural Evolution in Heat Treated Zr-2.5% Nb Pressure Tube Material Subjected to Dilatometric Studies

2011 ◽  
Vol 64 (4-5) ◽  
pp. 395-399 ◽  
Author(s):  
R. V. Kulkarni ◽  
S. Neogy ◽  
B. N. Rath ◽  
K. Manikrishna ◽  
D. Srivastava ◽  
...  
Keyword(s):  
Pressure Tube ◽  
Tube Material ◽  
Textural Evolution ◽  
Heat Treated ◽  
Dilatometric Studies

Effect of radial hydride fraction on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between ambient and 300 °C temperatures

2018 ◽  
Vol 508 ◽  
pp. 546-555 ◽  
Author(s):  
Rishi K. Sharma ◽  
A.K. Bind ◽  
G. Avinash ◽  
R.N. Singh ◽  
Asim Tewari ◽  
...  
Keyword(s):  
Fracture Toughness ◽  
Pressure Tube ◽  
Tube Material
Sign in / Sign up

Export Citation Format

Share Document