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51313-02539-Outside Diameter Stress Corrosion Cracking of Stainless Steel in Light Water Reactors

Product Number: 51313-02539-SG
ISBN: 02539 2013 CP
Author: Barry Gordon
Publication Date: 2013
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While stress corrosion cracking (SCC) is a major service life limiting mechanism for both pressurized water reactors (PWRs) and boiling water reactors (BWRs) most of the corrosion research emphasis in the nuclear corrosion community has been focused on SCC on materials wetted by the coolant. However SCC also occurs on the outside surfaces of austenitic stainless steels exposed to only the atmosphere. This paper will present some history of this corrosion concern in nuclear reactors and discuss the environmental conditions where outside diameter stress corrosion cracking (ODSCC) of stainless steel can occur the specific parameters that affect ODSCC such as chloride surface concentration and relative humidity and the various guidelines for surface cleanliness for ODSCC mitigation.

While stress corrosion cracking (SCC) is a major service life limiting mechanism for both pressurized water reactors (PWRs) and boiling water reactors (BWRs) most of the corrosion research emphasis in the nuclear corrosion community has been focused on SCC on materials wetted by the coolant. However SCC also occurs on the outside surfaces of austenitic stainless steels exposed to only the atmosphere. This paper will present some history of this corrosion concern in nuclear reactors and discuss the environmental conditions where outside diameter stress corrosion cracking (ODSCC) of stainless steel can occur the specific parameters that affect ODSCC such as chloride surface concentration and relative humidity and the various guidelines for surface cleanliness for ODSCC mitigation.

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