The U.K. Fast Reactor Materials Programme

Harries,; Standring, J.; Barnes, W.D.; Lloyd, G.J.

doi:10.1520/stp34405s

Cited by 4 publications

(3 citation statements)

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“…Applying the natural logarithm on both sides of Equation ( 4), the correlation between strain rate and stress is given by Equation ( 5)- (7).…”

Section: Constitutive Equationmentioning

confidence: 99%

“…[1][2][3][4] With the development of nuclear power and the discovery of irradiation-induced void swelling, improving the radiation resistance of materials is crucial for the rapid selection of reactor core materials. [5][6][7] Bloom et al [8] proposed the concept of reduced activation materials based on replacing easily activated elements with low-activation elements. Consequently, reduced-activation ferritic/martensitic (RAFM) steels with good radiation resistance were developed in the 1980s and have been widely used for fabricating fuel assemblies irradiated in various fast reactors worldwide.…”

Section: Introductionmentioning

confidence: 99%

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Constitutive Equation for the Hot Deformation and Microstructure Evolution of 12Cr‐F/M Steel

Yue

Lin

et al. 2023

steel research int.

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Ferrite/martensite steel is an important material candidate for nuclear reactor claddings owing to its excellent mechanical properties and radiation resistance. In particular, the hot deformation behavior of 12Cr‐ferritic/martensitic (12Cr‐F/M) steel is crucial for the fabrication of cladding tubes, and experiments performed in a wide temperature range could reveal the possible thermal deformation behavior of 12Cr‐F/M steel during tube fabrication. Herein, hot compression experiments of 12Cr‐F/M steel are conducted with strain rates and deformation temperatures ranging from 0.005 to 5 s−1 and 750 to 1200 °C, respectively. According to the thermal deformation flow and thermal expansion curves of the alloy, the Arrhenius‐type constitutive equations before and after the phase transformation of 12Cr‐F/M steel are established, taking 950 °C as the critical point. The results show that for a strain rate of 0.5 s−1, the cooling intensity increases gradually with the deformation temperature. The ferrite transforms into a mixed structure of ferrite and pearlite and finally transforms into martensite. At 950 °C, the degree of austenitization of the alloy increases with the strain rate, and the texture changes from cubic to brass.

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“…Applying the natural logarithm on both sides of Equation ( 4), the correlation between strain rate and stress is given by Equation ( 5)- (7).…”

Section: Constitutive Equationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Constitutive Equation for the Hot Deformation and Microstructure Evolution of 12Cr‐F/M Steel

Yue

Lin

et al. 2023

steel research int.

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“…First developed by the British in 1950s, the 20Cr25Ni/Nb stainless steel has been used as a fuel cladding material for the British Advanced Gas-cooled Reactor (AGR) fleet since 1962 [6].…”

Section: A709(nf709)mentioning

confidence: 99%

Evaluation of LPBF Steels for Nuclear Applications

Mantri¹,

Zhang²

2023

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Effects of Thermal Aging on Precipitate Development of Alloy Ht-9

Wilcox

1990

Effects of Radiation on Materials: 14th International Symposium (Volume I)

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Electron microscopy of carbon extraction replicas was performed to identify and evaluate precipitate evolution in the 12Cr-1Mo ferritic-martensitic alloy HT-9 during long-term aging of two different heats, 84425 and 91354. All samples were heat treated at 1078°C/0.5 h/AC + 760°C/2 h/AC. Thermal aging was conducted in the temperature range of 500 to 800°C and for 30 to 10 000 h. Precipitates were identified using electron microdiffraction patterns and energy dispersive X-ray spectroscopy (EDX) analysis. M23C6, MX. Laves. M3X phases, and aluminum oxide (Al2O3) inclusions were found in various specimens of both heats, while the M2X phase and manganese sulfide (MnS) inclusions were present only in some of the 91354 series specimens. M23C6 was the predominant precipitate in all samples. The MX phase was found in all samples from Heat 91354 but was not found below 700°C in the 84425 series. The Laves phase was present up to 700°C in both heats. M3X was found at 800°C in both series and also after long-term aging at 700 and 750°C in 91354.

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The U.K. Fast Reactor Materials Programme

Cited by 4 publications

References 0 publications

Constitutive Equation for the Hot Deformation and Microstructure Evolution of 12Cr‐F/M Steel

Constitutive Equation for the Hot Deformation and Microstructure Evolution of 12Cr‐F/M Steel

Evaluation of LPBF Steels for Nuclear Applications

Effects of Thermal Aging on Precipitate Development of Alloy Ht-9

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