Tensile Properties of Neutron-Irradiated Nimonic PE16

Bajaj, R.; Shogan, R.P.; DeFlitch, C; Fish, R.L.; Paxton, MM; Bleiberg, M.L.

doi:10.1520/stp28222s

Cited by 8 publications

(7 citation statements)

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“…Figure 4. A significant decrease in the total elongation of Nimonic PE16 when tested at (a) the irradiation temperature (T irrad ) and (b) 110 K above T irrad [6].…”

Section: Discussionmentioning

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

Angeliu

Ward

Witter

2007

Journal of Nuclear Materials

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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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“…Figure 4. A significant decrease in the total elongation of Nimonic PE16 when tested at (a) the irradiation temperature (T irrad ) and (b) 110 K above T irrad [6].…”

Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Assessing the effects of radiation damage on Ni-base alloys for the prometheus space reactor system

Angeliu

Ward

Witter

2007

Journal of Nuclear Materials

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“…The authors argued against grain boundary weakening mechanisms such as He embrittlement and solute segregation, but no direct evidence was provided showing that these mechanisms were not operating. In fact, data used to advocate that helium embrittlement was not applicable were found to be statistically insignificant [44].…”

Section: Review Of Mechanical Testmentioning

confidence: 98%

“…Number of Disnlacements (dnal Figure 6 A significant decrease in the total elongation of Nimonic PE16 when tested at (a) the irradiation temperature (Tirrad) and (b) 110 K above Timd [6].…”

Section: Review Of Mechanical Testmentioning

confidence: 99%

“…In the second example, solution annealed (not aged) PE16 was irradiated in EBR-I1 at fluences of 180, 430 and 710x10~~ nlcm2 at temperatures ranging from 723 K to 1008 K [6]. Tensile specimens were tested at 400 K, representing refueling temperatures for EBR-II, the irradiation temperature and 110 K above the irradiation temperature, representative of a temperature excursion.…”

Section: Review Of Mechanical Testmentioning

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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Contributions from research on irradiated ferritic/martensitic steels to materials science and engineering

Gelles

1990

Metall Trans A

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Tensile Properties of Neutron-Irradiated Nimonic PE16

Cited by 8 publications

References 0 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

Contributions from research on irradiated ferritic/martensitic steels to materials science and engineering

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