Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR

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Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR. / Bosch, Rik-Wouter; Van Renterghem, Wouter; Van Dyck, Steven; Chaouadi, Rachid; Gérard, Robert; Somville, Frédéric.

In: Journal of Nuclear Materials, Vol. 543, 152615, 24.10.2020, p. 1-18.

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@article{42978a0b85fd44a2ac78e24f072f6e2c,
title = "Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR",
abstract = "Neutron irradiation in the core of a nuclear power plant can change the material properties of stainless steel significantly. In this paper cold worked AISI 316 baffle bolts retrieved from Doel 1 PWR were investigated with the aim to assess the structural degradation due to neutron irradiation by analyzing microstructure, mechanical behavior and stress corrosion susceptibility. The baffle bolts had received neutron doses ranging from 6 to 59 dpa covering a major part of a nuclear power plant’s lifetime. First, microstructural investigations were carried out to reveal the defect and dislocation density and the amount of void swelling. Then mechanical properties were determined using tensile tests and fracture toughness tests. The irradiation assisted stress corrosion cracking (IASCC) susceptibility was investigated by slow strain rate testing and crack growth rate testing. Results were compared with literature values and found to be in good agreement. Main conclusions were that void swelling was small even for the highest dpa values and that the fracture toughness values saturated above 15 dpa. The material was susceptible to IASCC as shown by SSRT and crack growth rate measurements exhibiting intergranular fracture morphology.",
keywords = "Baffle bolt, PWR, Void swelling, fracture toughness, IASCC",
author = "Rik-Wouter Bosch and {Van Renterghem}, Wouter and {Van Dyck}, Steven and Rachid Chaouadi and Robert G{\'e}rard and Fr{\'e}d{\'e}ric Somville",
note = "Score=10",
year = "2020",
month = "10",
day = "24",
doi = "10.1016/j.jnucmat.2020.152615",
language = "English",
volume = "543",
pages = "1--18",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

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TY - JOUR

T1 - Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR

AU - Bosch, Rik-Wouter

AU - Van Renterghem, Wouter

AU - Van Dyck, Steven

AU - Chaouadi, Rachid

AU - Gérard, Robert

AU - Somville, Frédéric

N1 - Score=10

PY - 2020/10/24

Y1 - 2020/10/24

N2 - Neutron irradiation in the core of a nuclear power plant can change the material properties of stainless steel significantly. In this paper cold worked AISI 316 baffle bolts retrieved from Doel 1 PWR were investigated with the aim to assess the structural degradation due to neutron irradiation by analyzing microstructure, mechanical behavior and stress corrosion susceptibility. The baffle bolts had received neutron doses ranging from 6 to 59 dpa covering a major part of a nuclear power plant’s lifetime. First, microstructural investigations were carried out to reveal the defect and dislocation density and the amount of void swelling. Then mechanical properties were determined using tensile tests and fracture toughness tests. The irradiation assisted stress corrosion cracking (IASCC) susceptibility was investigated by slow strain rate testing and crack growth rate testing. Results were compared with literature values and found to be in good agreement. Main conclusions were that void swelling was small even for the highest dpa values and that the fracture toughness values saturated above 15 dpa. The material was susceptible to IASCC as shown by SSRT and crack growth rate measurements exhibiting intergranular fracture morphology.

AB - Neutron irradiation in the core of a nuclear power plant can change the material properties of stainless steel significantly. In this paper cold worked AISI 316 baffle bolts retrieved from Doel 1 PWR were investigated with the aim to assess the structural degradation due to neutron irradiation by analyzing microstructure, mechanical behavior and stress corrosion susceptibility. The baffle bolts had received neutron doses ranging from 6 to 59 dpa covering a major part of a nuclear power plant’s lifetime. First, microstructural investigations were carried out to reveal the defect and dislocation density and the amount of void swelling. Then mechanical properties were determined using tensile tests and fracture toughness tests. The irradiation assisted stress corrosion cracking (IASCC) susceptibility was investigated by slow strain rate testing and crack growth rate testing. Results were compared with literature values and found to be in good agreement. Main conclusions were that void swelling was small even for the highest dpa values and that the fracture toughness values saturated above 15 dpa. The material was susceptible to IASCC as shown by SSRT and crack growth rate measurements exhibiting intergranular fracture morphology.

KW - Baffle bolt

KW - PWR

KW - Void swelling

KW - fracture toughness

KW - IASCC

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/overview/42745745

U2 - 10.1016/j.jnucmat.2020.152615

DO - 10.1016/j.jnucmat.2020.152615

M3 - Article

VL - 543

SP - 1

EP - 18

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

M1 - 152615

ER -

ID: 6961479