Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water

PL Andresen, J Hickling, A Ahluwalia, J Wilson - Corrosion, 2008 - meridian.allenpress.com
Stress corrosion cracking (SCC) of Alloy 600 (UNS N06600) and Alloys 182 (UNS W86182),
132 (UNS W86132), and 82 (UNS N06082) weld metals in high-temperature water is …

[HTML][HTML] Some fundamental understandings of Zn-injection water chemistry on material corrosion in pressurized water reactor primary circuit

X Wu, X Liu, Z Zhang, J Tan, EH Han, W Ke - Corrosion Communications, 2022 - Elsevier
The optimization of water chemistry in pressurized water reactor (PWR) primary circuit is one
of the most effective ways to achieve both safety and economy for operating PWR nuclear …

Water chemistry technology–one of the key technologies for safe and reliable nuclear power plant operation

S Uchida, Y Katsumura - Journal of Nuclear Science and …, 2013 - Taylor & Francis
Water chemistry control is one of the key technologies to establish safe and reliable
operation of nuclear power plants. Continuous and collaborative efforts of plant …

[HTML][HTML] Role of Zn injection on mitigating stress corrosion cracking initiation of Alloy 182 weld metal in simulated light water reactor environment

K Chen, A Mackiewicz, HP Seifert, S Virtanen, S Ritter - Corrosion Science, 2023 - Elsevier
The stress corrosion cracking (SCC) behaviour of nickel-based weld metal Alloy 182 was
studied in simulated light water reactor environments with or without zinc (Zn) addition …

[PDF][PDF] Zn injection in Pressurized Water Reactors–laboratory tests, field experience and modelling

I Betova, M Bojinov, P Kinnunen… - Research Report No. VTT …, 2011 - publications.vtt.fi
In recent years, fuel performance and environmental issues take an important place in
nuclear industry and consequently a number of objectives requested for an optimal water …

Stress corrosion behaviors of 316LN stainless steel in a simulated PWR primary water environment

Y Huang, W Wu, S Cong, G Ran, D Cen, N Li - Materials, 2018 - mdpi.com
The effect of the strain rate, experimental temperature, Zn content in the test solution, and
prefilming time on the mechanical properties was investigated by a tensile test with a slow …

Effects of hydrogen on SCC growth rate of Ni alloys in BWR water

PL Andresen, P Chou - Proceedings of the 15th International Conference …, 2016 - Springer
In boiling water reactors (BWRs), stress corrosion cracking (SCC) has occurred in Alloy 600
and Alloy 182, 132 and 82 weld metals. Most BWRs mitigated SCC by injecting H 2 into the …

Corrosion of structural materials and electrochemistry in high temperature water of nuclear power systems

S Uchida - Power Plant Chemistry, 2008 - inis.iaea.org
[en] The latest experiences with corrosion in the cooling systems of nuclear power plants are
reviewed. High temperature cooling water causes corrosion of structural materials, which …

Effect of dissolved H2 on SCC of Ni alloys and weld metals

PL Andresen, J Hickling, A Ahluwalia, J Wilson - NACE CORROSION, 2009 - onepetro.org
Stress corrosion cracking (SCC) of nickel alloys such as Alloy 600 and Alloy 182, 132 and
82 weld metals in high temperature water is important because these materials are widely …

SCC of Alloy 182 and 82 weld metals in BWR water

PL Andresen - NACE CORROSION, 2010 - onepetro.org
INTRODUCTION ABSTRACT The stress corrosion crack growth rate was evaluated on
controlled chemistries of Alloy 182 and Alloy 82 weld metals in 288° C BWR water …