Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR

Chen, Xiang; Sokolov, Mikhail A.

doi:10.2172/1829200

Cited by 3 publications

(4 citation statements)

References 4 publications

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“…For each BFB, four bend-bar specimens and seven thin-slice specimens were machined. The bend-bar specimens were used in the fracture toughness and fatigue crack growth rate studies [2]. In contrast, the thin-slice specimens were designated for microstructural analyses [3] and advanced mechanical testing [5].…”

Section: Harvested Baffle-former Boltsmentioning

confidence: 99%

“…Two high-fluence BFBs were successfully harvested from a Westinghouse PWR in 2016 and received at the Westinghouse facility for specimen fabrication. The manufactured specimens (thin plates) were delivered to ORNL, where fracture mechanics testing [1,2], advanced microstructure analysis [3,4], and pilot in situ mechanical tests [5] were performed.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors

Gussev,

Lach,

Chen

2023

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Section: Harvested Baffle-former Boltsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors

Gussev,

Lach,

Chen

2023

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“…In FY 2021, fracture toughness and fatigue crack growth rate (FCGR) testing of machined bend bar specimens from two harvested baffle former bolts were performed [36]. The main findings are summarized as follows:…”

Section: Post-irradiation Of Examination Of Baffle Former Boltsmentioning

confidence: 99%

Light Water Reactor Sustainability: Program Materials Research Pathway (FY22 Technical Program Plan)

Rosseel¹,

Chen²,

Rodriguez³

2022

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Components in operating commercial nuclear power plants must withstand very harsh environments that include extended time at neutron and gamma irradiation, stress, and temperature, as well as possible exposure to corrosive media. The many modes of materials degradation are complex and often include synergies between multiple environmental variables and conditions that vary depending on location and material. Understanding and managing materials degradation is a requirement for the continued safe and reliable operation of nuclear power plants.

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“…In FY 2021, fracture toughness and fatigue crack growth rate (FCGR) testing of machined bend bar specimens from two harvested baffle former bolts was performed [31]. The main findings are summarized as follows:…”

Section: Post-irradiation Of Examination Of Baffle Former Boltsmentioning

confidence: 99%

Light Water Reactor Sustainability Program Materials Research Pathway Technical Program Plan

Rosseel¹,

Chen²,

Rodriguez³

2021

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Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR

Cited by 3 publications

References 4 publications

Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors

Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors

Light Water Reactor Sustainability: Program Materials Research Pathway (FY22 Technical Program Plan)

Light Water Reactor Sustainability Program Materials Research Pathway Technical Program Plan

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