scholarly journals Effect of Neutron Irradiation on the Ductility of Austenitic Stainless Steel

1972 ◽  
Vol 16 (1) ◽  
pp. 45-54 ◽  
Author(s):  
E. E. Bloom ◽  
J. R. Weir
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Neutron Irradiation

The effect of neutron irradiation on the impact toughness of austenitic stainless steel in ultrafine-grained state

2021 ◽  
Vol 544 ◽  
pp. 152680
Author(s):  
Valentin K. Shamardin ◽  
Tatyana M. Bulanova ◽  
Alexander E. Fedoseev ◽  
Alexei A. Karsakov ◽  
Ruslan Z. Valiev ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Impact Toughness ◽  
Neutron Irradiation ◽  
Ultrafine Grained ◽  
The Impact

Mc Precipitate Characterization in Austenitic Stainless Steel

1980 ◽  
Vol 38 ◽  
pp. 384-385
Author(s):  
P. J. Maziasz ◽  
R. W. Carpenter
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Neutron Irradiation ◽  
Stainless Steels ◽  
Fusion Reactor ◽  
Austenitic Stainless Steels ◽  
Radiation Response ◽  
Unique Effect ◽  
Morphological Variants ◽  
Small Bubbles

MC precipitate particles in austenitic stainless steels have an important and unique effect on radiation response of these materials in a fusion reactor environment.Radiation-generated helium agglomerates at the precipitate/matrix interfaces in the form of small bubbles. There are two morphological variants of the precipitate and both have similar helium trapping behavior. In this note we describe initial observations of one crystallographic and morphological variant of MC in austenite, which is the dominant variant formed during neutron irradiation in HFIR.

Cyclic Crack Growth Rate of Irradiated Austenitic Stainless Steel Welds in Simulated BWR Environment

2011 ◽  
Author(s):  
Y. Chen ◽  
B. Alexandreanu ◽  
W. J. Shack ◽  
K. Natesan ◽  
A. S. Rao
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Crack Growth ◽  
Neutron Irradiation ◽  
Growth Rates ◽  
Reactor Core ◽  
Cracking Behavior ◽  
Steel Welds ◽  
The Impact ◽  
Crack Growth Rates

Reactor core internal components in light water reactors are subjected to neutron irradiation. It has been shown that the austenitic stainless steels used in reactor core internals are susceptible to stress corrosion cracking after extended neutron exposure. This form of material degradation is a complex phenomenon that involves concomitant conditions of irradiation, stress, and corrosion. Interacting with fatigue damage, irradiation-enhanced environmental effects could also contribute to cyclic crack growth. In this paper, the effects of neutron irradiation on cyclic cracking behavior were investigated for austenitic stainless steel welds. Post-irradiation cracking growth tests were performed on weld heat-affected zone specimens in a simulated boiling water reactor environment, and cyclic crack growth rates were obtained at two doses. Environmentally enhanced cracking was readily established in irradiated specimens. Crack growth rates of irradiated specimens were significantly higher than those of nonirradiated specimens. The impact of neutron irradiation on environmentally enhanced cyclic cracking behavior is discussed for different load ratios.

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