Performance of Aluminum in Research Reactors

Farrell, K.

doi:10.1016/b978-0-08-056033-5.00113-0

Cited by 23 publications

(24 citation statements)

References 53 publications

(66 reference statements)

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“…The data obtained by both techniques shows that, for both pH values, the outer layer consists of aluminum oxide hydroxide AlO(OH) (also expressed as Al 2 O 3 ÁH 2 O) called boehmite as was expected in water at 250°C, according to the data reported by Wintergerst [1]. Contrarily to the results reported in literature for experiments performed around 100°C (near the transition temperature from bayerite to boehmite) [5,15], bayerite was never observed during our experiments due to the high experimental temperature considered (250°C) compared to that associated to the stabilization of this phase [16,17].…”

Section: Characterization Of the Corroded Specimenscontrasting

confidence: 43%

Effects of pH, surface finish and thermal treatment on the corrosion of AlFeNi aluminum alloy. Characterization of oxide layers

Nabhan

Kapusta

Billaud

et al. 2015

Journal of Nuclear Materials

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Section: Characterization Of the Corroded Specimenscontrasting

confidence: 43%

Effects of pH, surface finish and thermal treatment on the corrosion of AlFeNi aluminum alloy. Characterization of oxide layers

Nabhan

Kapusta

Billaud

et al. 2015

Journal of Nuclear Materials

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“…A substantial amount of literature is published on the irradiation behavior of Al alloys [2][3][4][5][6][7][8][9][10][11]. The available dataset on 6xxx series alloys is considerably larger due to their widespread use in several research reactors and cold-neutron sources [2,[4][5][6][7][8][9][10]. On the other hand, only limited data were found on 5xxx series alloys [3,9,11,12].…”

Section: Literature On Irradiation Effects In Al Alloysmentioning

confidence: 99%

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Kolluri¹

2016

Radiation Effects in Materials

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A literature review on highly irradiated 5xxx and 6xxx series Al alloys is conducted to understand the expected changes in mechanical properties of high flux reactor (HFR) vessel material in relation with microstructural aspects beyond the current surveillance data to support the HFR Surveillance Program (SURP). It was found that the irradiation swelling in 5xxx series alloys is not a crucial degradation mechanism. Dislocation damage is expected to reach a saturation limit in both 5xxx and 6xxx series alloys at relatively low fast-fluence values (<2 × 10 26 n/m 2). The damage caused by precipitation of transmutation Si is found to be the dominant mechanism affecting the fracture toughness properties of irradiated 5xxx and 6xxx series Al alloys at high thermal fluence values. Tensile and fracture toughness data collected from the literature up to very high thermal fluences are analyzed in comparison with the available HFR surveillance data to predict the behavior of the HFR vessel material beyond current surveillance data. The observed changes in mechanical properties are classified into four different regimes. The contribution of various irradiation damage mechanisms, namely the displacement damage and transmutation damage, to the evolution of microstructure and mechanical properties is discussed in all four regimes for 5xxx and 6xxx series alloys.

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“…It is known that both the Al matrix and Al alloy cladding are dimensionally stable during irradiation and are quite inert from irradiation damage [16] [17]. For cases that are free of the above-mentioned large pores, fuel meat swelling is a sum of the swelling of the U-Mo kernels as a result of fission, and volume expansion due to IL growth [18].…”

Section: A N U S C R I P Tmentioning

confidence: 99%

Pore growth in U-Mo/Al dispersion fuel

Kim

Jeong

Jamison

2016

Journal of Nuclear Materials

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for submission U-Mo/Al dispersion fuel is currently under development in the DOE's Material Management andMinimization program to convert HEU-fueled research reactors to LEU-fueled reactors. In some demanding conditions in high-power and high-performance reactors, large pores form in the interaction layers between the U-Mo fuel particles and the Al matrix, which pose a potential to cause fuel failure. In this study, comprehension of the formation and growth of these pores was explored. As a product, a model to predict pore growth and porosity increase was developed.Well-characterized in-pile data from reduced-size plates were used to fit the model parameters. A data set of full-sized plates, independent and distinctively different from those used to fit the model parameters, was used to examine the accuracy of the model. Abstract U-Mo/Al dispersion fuel is currently under development in the DOE's Material Management andMinimization program to convert HEU-fueled research reactors to LEU-fueled reactors. In some demanding conditions in high-power and high-performance reactors, large pores form in the interaction layers between the U-Mo fuel particles and the Al matrix, which pose a potential to cause fuel failure. In this study, comprehension of the formation and growth of these pores was explored. As a product, a model to predict pore growth and porosity increase was developed. The model includes three major topics: fission gas release from the U-Mo and the IL to the pores, stress evolution in the fuel meat, and the effect of amorphous IL growth. Well-characterized inpile data from reduced-size plates were used to fit the model parameters. A data set from fullsized plates, independent and distinctively different from those used to fit the model parameters, was used to examine the accuracy of the model. The model showed fair agreement with the measured data. The model suggested that the growth of the IL has a critical effect on pore growth, as both its material properties and energetics are favorable to pore formation. Therefore, one area of the current effort, focused on suppressing IL growth, appears to be on the right track to improve the performance of this fuel.

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Performance of Aluminum in Research Reactors

Cited by 23 publications

References 53 publications

Effects of pH, surface finish and thermal treatment on the corrosion of AlFeNi aluminum alloy. Characterization of oxide layers

Effects of pH, surface finish and thermal treatment on the corrosion of AlFeNi aluminum alloy. Characterization of oxide layers

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Pore growth in U-Mo/Al dispersion fuel

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