Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl2 Solution

doi:10.11902/1005.4537.2014.223

Journal of Chinese Society for Corrosion and protection

2015, Vol. 35

Issue (6): 488-495 DOI: 10.11902/1005.4537.2014.223

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Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl₂ Solution

Yueling GUO^1,²,En-Hou HAN^1,²(

),Jianqiu WANG¹

1. Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2. National Center for Materials Service Safety, University of Science and Technology Beijing, Beijing 100083, China

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Abstract

Effect of post solution- and stress relief-treatment on the stress corrosion cracking (SCC) resistance via U-bend specimens test in 42% boiling MgCl₂ solution, as well as the microstructure, residual strain and mechanical properties of the forged 316LN stainless steel was studied. Results showed that the yield stress was reduced and the residual strain was eliminated through post solution-treatment for the forged steel. After immersion in boiling MgCl₂ solution for 24, 48 and 72 h, respectively, all the U-bend specimens of either the solution-treated or the stress relief-treated steels suffered from clearly transgranular stress corrosion cracking (TGSCC). Furthermore, of which all the stress relief-treated specimens were entirly cracked, while the solution-treated specimens were only locally cracked after immersion for 72 h, suggesting higher SCC resistance for the forged steel after a proper post solution-treatment. Finally, the mechanism of the effect of post-heat treatments on the SCC resistance was discussed in terms of the residual strain and yield stress of the forged steel.

Key words: stainless steel nuclear materials heat treatment stress corrosion cracking magnesium chloride solution fractography

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	Yueling GUO
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Yueling GUO,En-Hou HAN,Jianqiu WANG. Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl₂ Solution. Journal of Chinese Society for Corrosion and protection, 2015, 35(6): 488-495.

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https://www.jcscp.org/EN/10.11902/1005.4537.2014.223 OR https://www.jcscp.org/EN/Y2015/V35/I6/488

Table 1 Mechanical properties of 316LN stainless steel at room temperature

Fig.1 SEM fractography images of S41 (a) and S42 (b) samples after tensile tests at room temperature

Fig.2 Microstructures of S41 (a) and S42 (b) samples

Fig.3 Grain size distribution of S41 (a) and S42 (b) samples

Fig.4 Inclusions inside S41 (a) and S42 (b) samples

Table 2 Chemical compositions of the inclusions inside S41 and S42(atomic fraction / %)

Fig.5 EBSD LAM images of S41 (a) and S42 (b) samples

Fig.6 Image of the U-bend specimen before SCC test (a) and SEM image of the sample bottom surface (b)

Fig.7 SEM images of the SCC cracks on the bottom surface of the U-bend S41 (a) and S42 (b) samples after immersion in boiling MgCl₂ solution for 72 h, and the magnified image of square area in Fig.7a (c)

Fig.8 Macro fracture morphologies of S41 (a, c, e) and S42 (b, d, f) samples after SCC tests in boiling 42%MgCl₂ solution for 24 h (a, b), 48 h (c, d) and 72h (e, f)

Fig.9 SEM fracture morphologies of U-bend S41 (a) and S42 (b) samples after SCC tests in boiling MgCl₂ solution

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