Effects of low dose rate irradiation and thermal aging on reactor structural alloys

T. R. Allen; C. L. Trybus; J. I. Cole

doi:10.1016/S0022-3115(99)00010-0

Effects of low dose rate irradiation and thermal aging on reactor structural alloys

T. R. Allen
, C. L. Trybus
, J. I. Cole

Research output: Contribution to journal › Article › peer-review

19 Scopus citations

Abstract

As part of the EBR-II reactor materials surveillance program, test samples of fifteen different alloys were placed into EBR-II in 1965. The surveillance (SURV) program was intended to determine property changes in reactor structural materials caused by irradiation and thermal aging. In this work, the effect of low dose rate (approximately 2×10^-8 dpa/s) irradiation at 380-410 °C and long term thermal aging at 371 °C on the properties of 20% cold worked 304 stainless steel, 420 stainless steel, Inconel X750, 304 308 stainless weld material, and 17-4 PH steel are evaluated. Doses of up to 6.8 dpa and thermal aging to 2994 days did not significantly affect the density of these alloys. The strength of 304 SS, X750, 17-4 PH, and 304/308 weld material increased with irradiation. In contrast, the strength of 420 stainless steel decreased with irradiation. Irradiation decreased the impact energy in both Inconel X750 and 17-4 PH steel. Thermal aging decreased the impact energy in 17-4 PH steel and increased the impact energy in Inconel X750. Tensile property comparisons of 304 SURV samples with 304 samples irradiated in EBR-II at a higher dose rate show that the higher dose rate samples had greater increases in strength and greater losses in ductility.

Original language	English
Pages (from-to)	290-300
Number of pages	11
Journal	Journal of Nuclear Materials
Volume	270
Issue number	3
DOIs	https://doi.org/10.1016/S0022-3115(99)00010-0
State	Published - Apr 2 1999
Externally published	Yes

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title = "Effects of low dose rate irradiation and thermal aging on reactor structural alloys",

abstract = "As part of the EBR-II reactor materials surveillance program, test samples of fifteen different alloys were placed into EBR-II in 1965. The surveillance (SURV) program was intended to determine property changes in reactor structural materials caused by irradiation and thermal aging. In this work, the effect of low dose rate (approximately 2×10-8 dpa/s) irradiation at 380-410 °C and long term thermal aging at 371 °C on the properties of 20\% cold worked 304 stainless steel, 420 stainless steel, Inconel X750, 304 308 stainless weld material, and 17-4 PH steel are evaluated. Doses of up to 6.8 dpa and thermal aging to 2994 days did not significantly affect the density of these alloys. The strength of 304 SS, X750, 17-4 PH, and 304/308 weld material increased with irradiation. In contrast, the strength of 420 stainless steel decreased with irradiation. Irradiation decreased the impact energy in both Inconel X750 and 17-4 PH steel. Thermal aging decreased the impact energy in 17-4 PH steel and increased the impact energy in Inconel X750. Tensile property comparisons of 304 SURV samples with 304 samples irradiated in EBR-II at a higher dose rate show that the higher dose rate samples had greater increases in strength and greater losses in ductility.",

author = "Allen, \{T. R.\} and Trybus, \{C. L.\} and Cole, \{J. I.\}",

note = "Funding Information: Thanks to W.E. Ruther, J.D. Staffon, G.O. Hayner, B.G. Carlson, and E.R. Ebersole for the data collection that made this analysis possible. Thanks to K.N. Grimm and K.A. Bunde for performing dose calculations and to R.T. Jensen for performing the temperature calculations. Work supported under contract W-31-109-Eng-38 with the US Department of Energy.",

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AU - Allen, T. R.

AU - Trybus, C. L.

AU - Cole, J. I.

N1 - Funding Information: Thanks to W.E. Ruther, J.D. Staffon, G.O. Hayner, B.G. Carlson, and E.R. Ebersole for the data collection that made this analysis possible. Thanks to K.N. Grimm and K.A. Bunde for performing dose calculations and to R.T. Jensen for performing the temperature calculations. Work supported under contract W-31-109-Eng-38 with the US Department of Energy.

PY - 1999/4/2

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N2 - As part of the EBR-II reactor materials surveillance program, test samples of fifteen different alloys were placed into EBR-II in 1965. The surveillance (SURV) program was intended to determine property changes in reactor structural materials caused by irradiation and thermal aging. In this work, the effect of low dose rate (approximately 2×10-8 dpa/s) irradiation at 380-410 °C and long term thermal aging at 371 °C on the properties of 20% cold worked 304 stainless steel, 420 stainless steel, Inconel X750, 304 308 stainless weld material, and 17-4 PH steel are evaluated. Doses of up to 6.8 dpa and thermal aging to 2994 days did not significantly affect the density of these alloys. The strength of 304 SS, X750, 17-4 PH, and 304/308 weld material increased with irradiation. In contrast, the strength of 420 stainless steel decreased with irradiation. Irradiation decreased the impact energy in both Inconel X750 and 17-4 PH steel. Thermal aging decreased the impact energy in 17-4 PH steel and increased the impact energy in Inconel X750. Tensile property comparisons of 304 SURV samples with 304 samples irradiated in EBR-II at a higher dose rate show that the higher dose rate samples had greater increases in strength and greater losses in ductility.

AB - As part of the EBR-II reactor materials surveillance program, test samples of fifteen different alloys were placed into EBR-II in 1965. The surveillance (SURV) program was intended to determine property changes in reactor structural materials caused by irradiation and thermal aging. In this work, the effect of low dose rate (approximately 2×10-8 dpa/s) irradiation at 380-410 °C and long term thermal aging at 371 °C on the properties of 20% cold worked 304 stainless steel, 420 stainless steel, Inconel X750, 304 308 stainless weld material, and 17-4 PH steel are evaluated. Doses of up to 6.8 dpa and thermal aging to 2994 days did not significantly affect the density of these alloys. The strength of 304 SS, X750, 17-4 PH, and 304/308 weld material increased with irradiation. In contrast, the strength of 420 stainless steel decreased with irradiation. Irradiation decreased the impact energy in both Inconel X750 and 17-4 PH steel. Thermal aging decreased the impact energy in 17-4 PH steel and increased the impact energy in Inconel X750. Tensile property comparisons of 304 SURV samples with 304 samples irradiated in EBR-II at a higher dose rate show that the higher dose rate samples had greater increases in strength and greater losses in ductility.

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U2 - 10.1016/S0022-3115(99)00010-0

DO - 10.1016/S0022-3115(99)00010-0

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AN - SCOPUS:0032667081

SN - 0022-3115

VL - 270

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 3

ER -

Effects of low dose rate irradiation and thermal aging on reactor structural alloys

Abstract

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