The microstructure of fast neutron irradiated Nimonic PE16

Boothby, R.M.

doi:10.1016/0022-3115(96)00169-9

Cited by 24 publications

(21 citation statements)

References 15 publications

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“…These initial studies also showed that aging treatments applied to both solution annealed and cold worked alloys increased swelling, but the reason was not fully understood. Additional swelling studies with PE16 in EBR-II produced less than 1% swelling after irradiation between 44 to 77 dpa (880x10~~ to 1500x1020 n/cm2) at 667 to 909 K [7]. Lower swelling was also reported for PE16 containin 25 ppm B rather than 50 ppm B after irradiation in the Dounreay Fast Reactor up to 900x10 Swelling studies on solid solution strengthened Ni-base alloys have focused on Alloy 625, Hastelloy X and Alloy 800.…”

Section: Radiation-induced Swellingmentioning

confidence: 97%

“…several embrittlement mechanisms were proposed, including differential strengthening with radiation-induced precipitation of grain boundary phases [6iand the formation o i He bubbles on grain boundaries [7]. Due to this embrittlement, Ni-base alloys were abandoned in favor of swelling and embrittlement resistant austenitic and ferritic / martensitic steels [a].…”

Section: Heatmentioning

confidence: 99%

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Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Angeliu¹

2006

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Dear Sir:This letter provides, for information, a review of the effects of radiation damage on nickel-base alloys to support pre-conceptual Prometheus-1 design efforts. SummaryNi-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of -900 K for 15 years and fluences up to 1 6 0 x 1 0~~ n/cm2 (E>0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron ,exposure. While the mechanism responsible for radiation-induced embrittlement is not fully understood, it is likely a combination of helium ernbrittlement and solute segregation that can be highly dependent on the alloy composition and exposure conditions. Transmutation calculations show that detrimental helium levels would be expected at the end of life for the inner safety rod vessel (thimble) and possibly the outer pressure vessel, primarily from high energy (E>1 MeV) n,a reactions with "~i . Helium from 'OB is significant only for the outer vessel due to the proximity of the outer vessel to the Be0 control elements. Recommendations for further assessments of the material behavior and methods to minimize the effects of radiation damage through alloy design are provided.

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Section: Radiation-induced Swellingmentioning

confidence: 97%

Section: Heatmentioning

confidence: 99%

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Angeliu¹

2006

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“…Additional swelling studies with PE16 in EBR-II produced less than 1% swelling after irradiation between 44 to 77 dpa (880x10 20 to 1500x10 20 n/cm 2 ) at 667 to 909 K [7]. Lower swelling was also reported for PE16 containing 25 wppm B rather than 50 wppm B after irradiation in the Dounreay Fast Reactor up to 900x10 20 n/cm 2 (48 dpa) between 673 and 873 K [14,15].…”

Section: Radiation-induced Swellingmentioning

confidence: 99%

“…It is well documented that a continuous layer of γ' can form along the grain boundaries of irradiated, precipitation hardened Ni-base alloys, including solution annealed PE16 and has been associated with significant decreases in ductility [5,[40][41][42]. For aged PE16, the coverage of γ' on grain boundaries after irradiation is expected to be less pronounced than for solution annealed material and contribute less to embrittlement [7]. Wrought solid-solution strengthened Ni-base alloys that contain little to no elements that form intermetallics (Ti, Nb and Al) are believed to be less susceptible to this embrittlement.…”

Section: Radiation-induced Embrittlementmentioning

confidence: 99%

“…However, these materials were susceptible to radiation-induced grain boundary embrittlement. Several embrittlement mechanisms were proposed, including differential strengthening with radiation-induced precipitation of grain boundary phases [6] and the formation of He bubbles on grain boundaries [7]. Due to this embrittlement, Ni-base alloys were abandoned in favor of swelling and embrittlement resistant austenitic and ferritic / martensitic steels [8].…”

Section: Introductionmentioning

confidence: 99%

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Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Angeliu¹,

Ward²,

Witter³

2006

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Abstract. Ni-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of ~900 K for 15 years and fluences up to 160x10 20 n/cm 2 (E>0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron exposure. While the mechanism responsible for radiation-induced embrittlement is not fully understood, it is likely a combination of helium embrittlement and solute segregation that can be highly dependent on the alloy composition and exposure conditions. Transmutation calculations show that detrimental helium levels would be expected at the end of life for the inner safety rod vessel (thimble) and possibly the outer pressure vessel, primarily from high energy (E>1 MeV) n,α reactions with 58 Ni.Helium from 10 B is significant only for the outer vessel due to the proximity of the outer vessel to the BeO control elements. Recommendations for further assessments of the material behavior and methods to minimize the effects of radiation damage through alloy design are provided. 2PACS Code: 61.82.-d

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TEM investigation on the microstructural evolution of hastelloy N induced by Ar⁺ion irradiation

Liu

Lü

Liu

et al. 2013

Microsc. Res. Tech.

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Hastelloy N alloy has been selected as the primary structure material for molten salt reactor. In this article, Hastelloy N alloy samples were irradiated to different doses at room temperature using 300 keV Ar(+) ions. The microstructural evolution was investigated by transmission electron microscopy (TEM) and energy-dispersive spectroscopy (EDS). Black dot defects emerged in sample irradiated at low dose (0.4 displacement per atom (dpa)), and they grew up with irradiation doses (0.4-2 dpa). A high density of small dislocation loops (nano meters in size) were observed in the sample irradiated to 4 dpa. When the ion dose increased to 12 dpa, complicated structures with defects (including dislocation lines, larger loops and smaller black dots) were observed. Dislocation networks were detected from high-angle annular dark field (HAADF) images. Larger dislocation loops (size: 30-80 nm) were visible in the sample irradiated to 40 dpa. Irradiation with dose of 120 dpa led to the formation of face-centered cubic nanocrystallites with preferred orientations.

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The microstructure of fast neutron irradiated Nimonic PE16

Cited by 24 publications

References 15 publications

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

TEM investigation on the microstructural evolution of hastelloy N induced by Ar⁺ion irradiation

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The microstructure of fast neutron irradiated Nimonic PE16

Cited by 24 publications

References 15 publications

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

TEM investigation on the microstructural evolution of hastelloy N induced by Ar+ion irradiation

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TEM investigation on the microstructural evolution of hastelloy N induced by Ar⁺ion irradiation