Crack Initiation of Neutron-irradiated 304L Stainless Steel in PWR Primary Water

2021 ◽  
pp. 109902
Author(s):  
Donghai Du ◽  
Kai Sun ◽  
Gary S. Was
Author(s):  
Nicolas Huin ◽  
Kazuya Tsutsumi ◽  
Laurent Legras ◽  
Thierry Couvant ◽  
Dominique Loisnard ◽  
...  

The French Regulatory Commission insisted on a survey justifying the assumed mechanical behavior of components exposed to Pressurized Water Reactor (PWR) water under cyclic loading without taking into account its effect. In the US and Japan, the fatigue life correlation factors, so called Fen, are formulated and standardized on the basis of laboratory data to take into account the effect on fatigue life evaluation. However, the current fatigue codification, suffers from a lack of understanding of environmental effects on the fatigue lives of stainless steels in simulated hydrogenated PWR environments. Samples tested in a recent study were analyzed to highlight the strain rate effect (within a range 0.4%/s to 0.004%/s) at the early stage of fatigue life in PWR primary environment for a 304L stainless steel. The deleterious effect of PWR primary environment on fatigue crack initiation was observed with a quantitative microscopic approach. Multi scale observations of oxide morphology and microstructure were carried out from common optical microscopy using recent technologies such as 3D oxide reconstruction, and DualBeam observations.


2021 ◽  
Vol 556 ◽  
pp. 153258
Author(s):  
Kathleen Jaffré ◽  
Hiroshi Abe ◽  
Benoît Ter-Ovanessian ◽  
Nicolas Mary ◽  
Bernard Normand ◽  
...  

2019 ◽  
Vol 165 ◽  
pp. 203-214 ◽  
Author(s):  
Litao Chang ◽  
Liberato Volpe ◽  
Yong Liang Wang ◽  
M. Grace Burke ◽  
Agostino Maurotto ◽  
...  

Author(s):  
Kazuya Tsutsumi ◽  
Nicolas Huin ◽  
Thierry Couvant ◽  
Gilbert Henaff ◽  
Jose Mendez ◽  
...  

Over the last 20 years or so, many studies have revealed the deleterious effect of the environment on fatigue life of austenitic stainless steels in pressurized water reactor (PWR) primary water. The fatigue life correlation factor, so-called Fen, has been standardized to consider the effect on fatigue life evaluation. The formulations are function of strain rate and temperature due to their noticeable negative effect compared with other factors [1,2]. However, mechanism causing fatigue life reduction remains to be cleared. As one of possible approaches to examine underlying mechanism of environmental effect, the authors focused on the effect of plastic strain, because it could lead microstructural evolution on the material. In addition, in the case of stress corrosion cracking (SCC), it is well known that the strain-hardening prior to exposure to the primary water can lead to remarkable increase of the susceptibility to cracking [3,4]. However, its effect on fatigue life has not explicitly been investigated yet. The main effort in this study addressed the effect of the prior strain-hardening on low cycle fatigue life of 304L stainless steel (SS) exposed to the PWR primary water. A plate of 304LSS was strain hardened by cold rolling or tension prior to fatigue testing. The tests were performed under axial strain-controlled at 300 °C in primary water including B/Li and dissolved hydrogen, and in air. The effect on environmental fatigue life was investigated through a comparison of the Fen in experiments and in regulations, and also the effect on the fatigue limit defined at 106 cycles was discussed.


Author(s):  
John Hickling ◽  
Renate Kilian ◽  
Leslie Spain ◽  
John Carey

Environmental fatigue testing of small-scale austenitic stainless steel components under simulated pressurized water reactor (PWR) operating conditions was sponsored by the EPRI Materials Reliability Program (MRP) Fatigue Issue Task Group and the U.S. Department of Energy to fill in some important gaps in the knowledge base. An analysis and assessment of existing fatigue data for stainless steel exposed to the PWR primary environment identified a lack of data with respect to flow rate effects. The majority of existing data has been gained under static or quasi-static flow conditions, where the tendency to environmental enhancement of cyclic crack growth is generally expected to increase. However plant experience — where high-flow conditions prevail — shows significantly lower susceptibility to corrosion fatigue cracking. The main objective of the present test program was the identification of flow-rate effects on the initiation and growth of low-cycle corrosion fatigue (LCF) cracks in cold-drawn, 304L stainless steel tube U-bend specimens undergoing cyclic loading and simultaneous exposure to simulated PWR primary water on the inside of the tube. Use was made of a pre-existing facility at F-ANP in Germany where the experimental concept had been previously tested on carbon-steel U-bends. The test equipment was set up so as to allow direct comparison of results obtained under quasi-stagnant conditions (∼0.005 m/s flow rate at the internal surface) with relatively high-flow conditions (∼ 2.2 m/s flow rate). In accordance with literature data, PWR primary water was shown to have a significant effect on the high-temperature fatigue behavior of the bends, as demonstrated by the observed change in failure mode and location of cracking between baseline specimens (tested in nitrogen) and those bends exposed to simulated reactor coolant. Metallography and fractography suggest that the environment is acting by affecting both crack initiation and crack growth. In contrast to the situation for carbon steel, no beneficial effect of higher flow rate on the number of cycles to failure (leakage) was observed. The paper discusses further details of the environmental fatigue data obtained, including the effects of strain amplitude, strain rate and surface condition. It also provides a comparison of test results with the current ASME Section III fatigue curves.


1981 ◽  
Vol 42 (C5) ◽  
pp. C5-193-C5-198 ◽  
Author(s):  
N. Igata ◽  
H. B. Chen ◽  
K. Miyahara ◽  
T. Uba

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