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51313-02442-Effects of Plastic Strain and Stress Distribution on SCC Initiation in High-Temperature Water

Product Number: 51313-02442-SG
ISBN: 02442 2013 CP
Author: Yasufumi Miura
Publication Date: 2013
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Stress corrosion cracking (SCC) has been occurred in boiling water reactor (BWR) components such as reactor core shrouds and primary loop recirculation (PLR) pipes made of L-grade (low carbon) austenitic stainless steels which are not thermally sensitized. SCC cracking of reactor core shrouds and PLR pipes is generally initiated on work hardened surfaces. Therefore it is important to clarify the effect of work hardened surface layer on SCC initiation behavior. In this study X-ray stress measurement hardness testing and optical microscopy on a specimen with controlled plastic strain distribution were carried out in order to evaluate effects of plastic strain and stress distribution on SCC initiation. The following results were obtained. (1) Stress distribution on the specimen after bending was negatively correlated with hardness distribution on the specimen before bending. Stress in low hardness area was larger than the stress in high hardness area. (2) The relationship between hardness profiles and SCC initiated areas suggested that plastic deformation by bending and high hardness gradient increased SCC initiation susceptibility in the specimen.

Keywords
Boiling water reactor Type 316L stainless steel Stress corrosion cracking X-ray stress measurement Strain distribution
 

Stress corrosion cracking (SCC) has been occurred in boiling water reactor (BWR) components such as reactor core shrouds and primary loop recirculation (PLR) pipes made of L-grade (low carbon) austenitic stainless steels which are not thermally sensitized. SCC cracking of reactor core shrouds and PLR pipes is generally initiated on work hardened surfaces. Therefore it is important to clarify the effect of work hardened surface layer on SCC initiation behavior. In this study X-ray stress measurement hardness testing and optical microscopy on a specimen with controlled plastic strain distribution were carried out in order to evaluate effects of plastic strain and stress distribution on SCC initiation. The following results were obtained. (1) Stress distribution on the specimen after bending was negatively correlated with hardness distribution on the specimen before bending. Stress in low hardness area was larger than the stress in high hardness area. (2) The relationship between hardness profiles and SCC initiated areas suggested that plastic deformation by bending and high hardness gradient increased SCC initiation susceptibility in the specimen.

Keywords
Boiling water reactor Type 316L stainless steel Stress corrosion cracking X-ray stress measurement Strain distribution
 

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