In situ study of heavy ion induced radiation damage in NF616 (P92) alloy

Topbasi, Cem; Motta, Arthur T.; Kirk, Mark A.

doi:10.1016/j.jnucmat.2011.08.046

Cited by 26 publications

(26 citation statements)

References 7 publications

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“…[63][64][65][66][67][68][69] Such experiments allow irradiation concurrent with observation in a transmission electron microscope. A black dot damage microstructure is seen to dominate irradiated ferritic/martensitic alloys up to temperatures of at least 300°C.…”

Section: Mev Kr Irradiation Of Fe-cr Ferritic/ Martensitic Alloymentioning

confidence: 99%

Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies

Wirth

Kohnert

et al. 2015

J. Mater. Res.

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It is well established that exposure of metallic structural materials to irradiation environments results in significant microstructural evolution, property changes, and performance degradation, which limits the extended operation of current generation light water reactors and restricts the design of advanced fission and fusion reactors. Further, it is well recognized that these irradiation effects are a classic example of inherently multiscale phenomena and that the mix of radiation-induced features formed and the corresponding property degradation depend on a wide range of material and irradiation variables. This inherently multiscale evolution emphasizes the importance of closely integrating models with high-resolution experimental characterization of the evolving radiation-damaged microstructure. This article provides a review of recent models of the defect microstructure evolution in irradiated body-centered cubic materials, which provide good agreement with experimental measurements, and presents some outstanding challenges, which will require coordinated high-resolution characterization and modeling to resolve.

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Section: Mev Kr Irradiation Of Fe-cr Ferritic/ Martensitic Alloymentioning

confidence: 99%

Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies

Wirth

Kohnert

et al. 2015

J. Mater. Res.

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“…9%Cr F/M steel P92 specified in ASTM Standards [9] and developed by the Nippon Steel Corporation (with the designation NF616) has being used in boiler components for ultra supercritical power plants operating up to 620 C. P92 steel exhibits improved creeprupture properties compared to HT-9 (12Cre1MoVW, firstgeneration F/M steel developed for conventional power plants operating up to 565 C) [3] which makes it a promising candidate for cladding and duct applications in Sodium-Cooled Fast Reactor, one of the Generation IV nuclear energy systems [10].…”

Section: Introductionmentioning

confidence: 99%

Precipitate phases in normalized and tempered ferritic/martensitic steel P92

Shen

Liu

Shang

et al. 2015

Journal of Nuclear Materials

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“…Additionally, irradiation conditions can be easily controlled [7,8]. A large number of studies have reported the mechanical properties of F/M steels after irradiation with neutrons [6], Ne ions [9], Kr ions [10,11], H ions, He ions, and electron beams [12,13]. Inert gas, especially He, created by nuclear reaction has a significant influence on the microstructural evolution of structural materials exposed to neutrons in nuclear reactors.…”

Section: Introductionmentioning

confidence: 99%

“…Attributed to solution strengthening by W and Mo additions and precipitation strengthening by V and Nb additions on the basis of P91 steel, P92 steel exhibits excellent high temperature mechanical properties, which makes it a promising candidate material for in-core applications in sodium fast reactor (SFR) and fusion systems [11,18]. The irradiation response of P92 steel has received much attention in the past few years [10,11,[19][20][21][22].…”

Section: Introductionmentioning

confidence: 99%

“…The irradiation response of P92 steel has received much attention in the past few years [10,11,[19][20][21][22]. Most research focused on the microstructural evolution of P92 steel irradiated with Kr ions at 200 and 400 • C [10,11]; with Ar ions at room temperature, 290, 390, and 550 • C [19,20]; and with protons at 500 • C [21]. When F/M steels are used as fuel cladding in a fast reactor, the operating temperature is expected to approach 650-700 • C [18].…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

Liu

Shen

Zhu³

et al. 2018

Metals

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P92 steel was irradiated with Ar ion up to 10 dpa at 200, 400, and 700 • C. The effect of Ar ion irradiation on hardness was investigated with nanoindentation tests and microstructure analyses. It was observed that irradiation-induced hardening occurred in the steel after Ar ion irradiation at all three temperatures to 10 dpa. The steel exhibited significant hardening at 200 and 700 • C, and slight hardening at 400 • C under Ar ion irradiation. Difference in the magnitude of irradiation-induced hardening at different temperature in the steel is attributed to different changes in the microstructure of the steel that arose from the irradiation. Irradiation-induced hardening in the P92 steel irradiated at 200 • C is attributed to the occurrence of both dislocation loops and other fine irradiation defects during irradiation. Slight hardening in the steel irradiated at 400 • C mainly arises from the annihilation of defect clusters at this temperature. The occurrence of fine Ar bubbles with high number density during the Ar ion irradiation at 700 • C resulted in the significant hardening in the steel.

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In situ study of heavy ion induced radiation damage in NF616 (P92) alloy

Cited by 26 publications

References 7 publications

Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies

Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies

Precipitate phases in normalized and tempered ferritic/martensitic steel P92

Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

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