Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions

Corrosion Science ◽

10.1016/j.corsci.2012.02.008 ◽

2012 ◽

Vol 59 ◽

pp. 20-34 ◽

Author(s):

H.P. Seifert ◽

S. Ritter ◽

H.J. Leber

Keyword(s):

Crack Growth ◽

Corrosion Fatigue ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Light Water Reactor ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Water Reactor ◽

Fatigue Initiation

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Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 1

Corrosion Issues in Light Water Reactors ◽

10.1201/9781439824085.pt3 ◽

2007 ◽

Author(s):

U Ehrnsten ◽

A Roth ◽

H Seifert ◽

M Zamboch ◽

S Ritter ◽

...

Keyword(s):

Crack Growth ◽

Operating Conditions ◽

Light Water Reactor ◽

Low Alloy Steels ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Water Reactor ◽

Alloy Steels ◽

Reactor Operating

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Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 1: BWR/NWC Conditions

Corrosion Issues in Light Water Reactors ◽

10.1533/9781845693466.3.165 ◽

2007 ◽

pp. 165-185 ◽

Author(s):

S. Ritter ◽

H.P. Seifert ◽

B. Devrient ◽

A. Roth ◽

U. Ehrnstén ◽

...

Keyword(s):

Crack Growth ◽

Operating Conditions ◽

Light Water Reactor ◽

Low Alloy Steels ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Water Reactor ◽

Alloy Steels ◽

Reactor Operating

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Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions

Corrosion Science ◽

10.1016/j.corsci.2011.10.005 ◽

2012 ◽

Vol 55 ◽

pp. 61-75 ◽

Author(s):

H.P. Seifert ◽

S. Ritter ◽

H.J. Leber

Keyword(s):

Fatigue Crack ◽

Fatigue Crack Growth ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Light Water Reactor ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Corrosion Fatigue Crack ◽

Corrosion Fatigue Crack Growth

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Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 2: VVER conditions

Corrosion Issues in Light Water Reactors ◽

10.1533/9781845693466.3.186 ◽

2007 ◽

pp. 186-199

Author(s):

M. Ernestová ◽

M. Žamboch ◽

B. Devrient ◽

A. Roth ◽

U. Ehrnstén ◽

...

Keyword(s):

Crack Growth ◽

Operating Conditions ◽

Light Water Reactor ◽

Low Alloy Steels ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Water Reactor ◽

Alloy Steels ◽

Reactor Operating

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Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 2

Corrosion Issues in Light Water Reactors ◽

10.1201/9781439824085.ch13 ◽

2007 ◽

Author(s):

U Ehrnsten ◽

H Seifert ◽

A Roth ◽

S Ritter ◽

M Zamboch ◽

...

Keyword(s):

Crack Growth ◽

Operating Conditions ◽

Light Water Reactor ◽

Low Alloy Steels ◽

Growth Behaviour ◽

Crack Growth Behaviour ◽

Light Water ◽

Water Reactor ◽

Alloy Steels ◽

Reactor Operating

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Stress corrosion cracking (SCC) of austenitic stainless steels in high temperature light water reactor (LWR) environments

Understanding and Mitigating Ageing in Nuclear Power Plants ◽

10.1533/9781845699956.2.236 ◽

2010 ◽

pp. 236-307 ◽

Author(s):

P.L. Andresen

Keyword(s):

High Temperature ◽

Stress Corrosion ◽

Stress Corrosion Cracking ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Corrosion Cracking ◽

Light Water Reactor ◽

Light Water ◽

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Measurement of the Deformability of Austenitic Stainless Steels and Nickel-Base Alloys in Light Water Reactor Cores

Slow Strain Rate Testing for the Evaluation of Environmentally Induced Cracking: Research and Engineering Applications ◽

10.1520/stp12756s ◽

2009 ◽

pp. 83-83-19 ◽

Author(s):

P Dewes ◽

D Alter ◽

F Garzarolli ◽

R Hahn ◽

JL Nelson

Keyword(s):

Stainless Steels ◽

Austenitic Stainless Steels ◽

Light Water Reactor ◽

Light Water ◽

Water Reactor ◽

Reactor Cores ◽

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Slow strain rate tensile tests on irradiated austenitic stainless steels in simulated light water reactor environments

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2013.08.003 ◽

2014 ◽

Vol 269 ◽

pp. 38-44 ◽

Author(s):

Y. Chen ◽

A.S. Rao ◽

B. Alexandreanu ◽

K. Natesan

Keyword(s):

Strain Rate ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Tensile Tests ◽

Slow Strain Rate ◽

Light Water Reactor ◽

Light Water ◽

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Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor condition

Journal of Nuclear Materials ◽

10.1016/s0022-3115(01)00673-0 ◽

2001 ◽

Vol 299 (1) ◽

pp. 53-67 ◽

Author(s):

J. Gan ◽

G.S. Was ◽

R.E. Stoller

Keyword(s):

Microstructure Evolution ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Light Water Reactor ◽

Light Water ◽

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Fatigue crack growth behaviour in austenitic stainless steels subjected to superficial and entire hydrogenation

Materials Science and Engineering A ◽

10.1016/j.msea.2012.03.101 ◽

2012 ◽

Vol 548 ◽

pp. 118-125 ◽

Author(s):

Yoji Mine ◽

Akihiro Orita ◽

Kenichi Murakami ◽

Jean-Marc Olive

Keyword(s):

Fatigue Crack ◽

Fatigue Crack Growth ◽

Crack Growth ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Growth Behaviour ◽

Crack Growth Behaviour

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