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A Model to Predict Stress Corrosion Cracking of Welded StainlessSteel Canister

Published online by Cambridge University Press:  20 February 2017

Gen Nakayama*
Affiliation:
Research Laboratory, IHI Corporation, 1, Shin-nakahara-cho, Isogo-ku, Yokohama 235-8501, Japan
Yohei Sakakibara
Affiliation:
Research Laboratory, IHI Corporation, 1, Shin-nakahara-cho, Isogo-ku, Yokohama 235-8501, Japan
Tomomi Kouketsu
Affiliation:
Research Laboratory, IHI Corporation, 1, Shin-nakahara-cho, Isogo-ku, Yokohama 235-8501, Japan
Kouji Arakawa
Affiliation:
Research Laboratory, IHI Corporation, 1, Shin-nakahara-cho, Isogo-ku, Yokohama 235-8501, Japan
Yutaka Mizo
Affiliation:
Production Engineering Center, IHI Corporation
Iku Miyasaka
Affiliation:
Nuclear Power Operations, IHI Corporation
Yumiko Iwata
Affiliation:
Nuclear Power Operations, IHI Corporation
Susumu Kawakami
Affiliation:
Nuclear Power Operations, IHI Corporation
Hirotomo Setaka
Affiliation:
Plant Project Department, IHI Corporation
Naoki Hieda
Affiliation:
Kitakyushu Liquefied Natural Gas CO., Inc., Kitakyuushu, 804-0002, Japan
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Abstract

Fabricated stainless steel structures are susceptible to stress corrosioncracking (SCC), despite being placed in chloride-containing natural water orhumid atmospheres. The present paper describes a model that can define theconditions under which SCC is initiated and propagated, based on analyses ofactual SCC incidents induced at welded flanges of cylindrical stainless steelstructures.

Whenever the vitrified radioactive waste canister storage conditions deviate fromnormal and appropriate conditions due to earthquakes or tsunamis, the exposedcanisters are expected to suffer SCC within 400 hours to 7 years, according tothe analytical results obtained such as degree of sensitization, residual stressdistribution, chloride ion concentration, and temperature.

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Copyright
Copyright © Materials Research Society 2017 

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References

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