Neutron irradiation response of explosion-welded CuCrZr/316LN joints for ITER application

•Explosion-welded CuCrZr/316LN joints were neutron irradiated to 0.3 dpa at Tirr < 190 °C. Good structural integrity has been maintained.•Black-spot contrasts dominated the damage microstructure on both sides of the CuCrZr/316LN interface. They were all under 4 nm in average size and achieved num...

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Published inFusion engineering and design Vol. 169; p. 112620
Main Authors Yi, Xiaoou, Du, Yufeng, Li, Yihang, Han, Wentuo, Liu, Pingping, Yoshida, Kenta, Toyama, Takeshi, Chen, Jiming, Zhan, Qian, Wan, Farong, Ohnuki, Somei, Nagai, Yasuyoshi
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.08.2021
Elsevier Science Ltd
Subjects
CuCrZr/316LN
Diamond pyramid hardness
Enhanced diffusion
Explosion welding
Heat flux
Heat treatment
Interlayers
Mechanical properties
Microstructure
Neutron flux
Neutron irradiation
Neutrons
Radiation
Radiation damage
Structural integrity
Mechanical properties
Explosion welding
Neutron irradiation
CuCrZr/316LN
Microstructure
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Abstract •Explosion-welded CuCrZr/316LN joints were neutron irradiated to 0.3 dpa at Tirr < 190 °C. Good structural integrity has been maintained.•Black-spot contrasts dominated the damage microstructure on both sides of the CuCrZr/316LN interface. They were all under 4 nm in average size and achieved number densities on the order of 1022 m−3.•Radiation-enhanced diffusion might have favoured the dissolution of interlayers in pristine CuCrZr/316LN joints, and have accelerated the interfacial diffusion of key elements by at least two orders of magnitude.•The joint interface experienced an increase of Vickers hardness by ~ 21% after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening, respectively. Explosion-welded CuCrZr/316LN joints, which serve as key joining components in enhanced-heat-flux type first wall panels of ITER, have been neutron irradiated in the BR2 reactor (Belgium) at <190 °C, up to 0.3 dpa. The joints have maintained good structural integrity after irradiation and were free of void swelling. Radiation defects featuring black-spot contrasts were produced on both sides of the CuCrZr/316LN interface. They were on the order of 1022 m−3 in number density and all less than 4 nm in average size. Radiation-enhanced diffusion might have favoured the dissolution of interlayers which were characteristic of pristine CuCrZr/316LN joints, and accelerated the diffusion of key elements (e.g. Cu, Fe) across the interface. The joint interface experienced an increase of Vickers hardness by ~ 21% (∆Hv = 48) after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening of the interface, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening effect, respectively.
AbstractList Explosion-welded CuCrZr/316LN joints, which serve as key joining components in enhanced-heat-flux type first wall panels of ITER, have been neutron irradiated in the BR2 reactor (Belgium) at <190 °C, up to 0.3 dpa. The joints have maintained good structural integrity after irradiation and were free of void swelling. Radiation defects featuring black-spot contrasts were produced on both sides of the CuCrZr/316LN interface. They were on the order of 1022 m−3 in number density and all less than 4 nm in average size. Radiation-enhanced diffusion might have favoured the dissolution of interlayers which were characteristic of pristine CuCrZr/316LN joints, and accelerated the diffusion of key elements (e.g. Cu, Fe) across the interface. The joint interface experienced an increase of Vickers hardness by ~ 21% (∆Hv = 48) after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening of the interface, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening effect, respectively.
•Explosion-welded CuCrZr/316LN joints were neutron irradiated to 0.3 dpa at Tirr < 190 °C. Good structural integrity has been maintained.•Black-spot contrasts dominated the damage microstructure on both sides of the CuCrZr/316LN interface. They were all under 4 nm in average size and achieved number densities on the order of 1022 m−3.•Radiation-enhanced diffusion might have favoured the dissolution of interlayers in pristine CuCrZr/316LN joints, and have accelerated the interfacial diffusion of key elements by at least two orders of magnitude.•The joint interface experienced an increase of Vickers hardness by ~ 21% after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening, respectively. Explosion-welded CuCrZr/316LN joints, which serve as key joining components in enhanced-heat-flux type first wall panels of ITER, have been neutron irradiated in the BR2 reactor (Belgium) at <190 °C, up to 0.3 dpa. The joints have maintained good structural integrity after irradiation and were free of void swelling. Radiation defects featuring black-spot contrasts were produced on both sides of the CuCrZr/316LN interface. They were on the order of 1022 m−3 in number density and all less than 4 nm in average size. Radiation-enhanced diffusion might have favoured the dissolution of interlayers which were characteristic of pristine CuCrZr/316LN joints, and accelerated the diffusion of key elements (e.g. Cu, Fe) across the interface. The joint interface experienced an increase of Vickers hardness by ~ 21% (∆Hv = 48) after neutron irradiation. Heat treatments of 500 °C/1 h resulted in moderate softening of the interface, while 800 °C/1 h gave rise to a complete elimination of irradiation-induced hardening effect, respectively.
ArticleNumber 112620
Author Li, Yihang
Chen, Jiming
Han, Wentuo
Wan, Farong
Liu, Pingping
Zhan, Qian
Yoshida, Kenta
Nagai, Yasuyoshi
Du, Yufeng
Toyama, Takeshi
Ohnuki, Somei
Yi, Xiaoou
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  surname: Nagai
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  organization: Institute of Materials Research, Tohoku University, Narita-cho 2145-2, Oarai, Ibaraki 311-1313, Japan
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Keywords Mechanical properties
Explosion welding
Neutron irradiation
CuCrZr/316LN
Microstructure
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Snippet •Explosion-welded CuCrZr/316LN joints were neutron irradiated to 0.3 dpa at Tirr < 190 °C. Good structural integrity has been maintained.•Black-spot contrasts...
Explosion-welded CuCrZr/316LN joints, which serve as key joining components in enhanced-heat-flux type first wall panels of ITER, have been neutron irradiated...
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SubjectTerms CuCrZr/316LN
Diamond pyramid hardness
Enhanced diffusion
Explosion welding
Heat flux
Heat treatment
Interlayers
Mechanical properties
Microstructure
Neutron flux
Neutron irradiation
Neutrons
Radiation
Radiation damage
Structural integrity
Title Neutron irradiation response of explosion-welded CuCrZr/316LN joints for ITER application
URI https://dx.doi.org/10.1016/j.fusengdes.2021.112620
https://www.proquest.com/docview/2554664612
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