Crystallographic Texture and Volume Fraction of α and β Phases in Zr-2.5Nb Pressure Tube Material During Heating and Cooling

Fong, R.W.L.; Miller, Ronald Mellado; Saari, H.; Vogel, Sven C.

doi:10.1007/s11661-011-0914-6

Cited by 25 publications

(4 citation statements)

References 25 publications

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“…The lattice paramter at 1135 • C (just below the melting point of U-10Mo) of 3.630 Å was used for the a-axis of β-Zr, which was estimated using a lattice parameter at 850 • C [47] and a coefficient of thermal expansion of 9.7 × 10 −6 /K [48]. This lattice parameter is close to the experimentally obtained lattice parameter of 3.627 Å for Zr-2.5Nb at 1050 • C [49]. Furthermore, the lattice parameter of the a-axis for the γ-U at 1135 • C was estimated to be 3.538 Å using the room temperature lattice parameter and a coefficient of thermal expansion of 11.8 × 10 −6 /K [2].…”

Section: α-Zr Texturementioning

confidence: 72%

Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr

Takajo

Hollis

Cummins

et al. 2018

QuBS

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A uranium-molybdenum alloy clad in 6061 aluminum has the potential to lead to a wide application of low-enriched uranium fuels, replacing highly enriched uranium for research reactors. A Zr coating acts as a diffusion barrier between the fuel and the aluminum cladding. In this study, U-10Mo (mass %) was coated with Zr using a plasma spray technique recognized as a fast and economical coating method. Neutron time-of-flight diffraction was used to study the microstructure evolution by quantifying the phase fractions of involved phases as well as the texture evolution of U-10Mo and Zr during plasma spray coating with Zr. Quantitative texture analysis revealed that the texture was drastically changed for high coating temperatures, likely due to selective grain growth. Furthermore, the Zr coating showed a preferential orientation, which could be correlated with the initial texture of the uncoated U-10Mo. This could be explained by the epitaxial growth of the Zr on the U-10Mo substrate.

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Section: α-Zr Texturementioning

confidence: 72%

Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr

Takajo

Hollis

Cummins

et al. 2018

QuBS

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“…Heating the pre-oxidized sample at 1000°C (Figure 5a) essentially dissolved the oxide as post-test sample showed little or no oxide remaining (i.e., an interference colour or a shiny surface was observed on the sample). At 1000°C, the un-oxidized and pre-oxidized samples are both a 100% beta-phase material [10]; essentially without any oxide layers on the surfaces in these 2 samples the resulting emissivity values are expected to be the same, as shown in Figures 5a and 5b. In comparison with Figure 4b for the un-oxidized sample with 50% beta-phase composition at 800°C, an increase to a 100% beta-phase composition when heated at 1000°C appeared to decrease the emissivity value to 0.25.…”

Section: Instantaneous and Steady-state Values Of Emissivitymentioning

confidence: 91%

“…Heating at 800°C induces an increased fraction of beta-Zr phase material (body-centered cubic structure) with a proportionate decrease of alpha-Zr phase (a hexagonal closepacked structure that is stable at lower temperatures than the beta-Zr phase) in the Zr-2.5Nb pressure-tube material. At 800°C, there is about an equal volume fraction (50%-50%) of alpha-and beta-phase materials [10]. Figure 5 compares the tests at 1000°C between pre-oxidized and un-oxidized samples.…”

Section: Instantaneous and Steady-state Values Of Emissivitymentioning

confidence: 99%

TOTAL HEMISPHERICAL EMISSIVITY OF PRE-OXIDIZED AND UN-OXIDIZED ZR-2.5Nb PRESSURE-TUBE MATERIALS AT 600 °C TO 1000 °C UNDER VACUUM

2016

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The emissivity of pre-oxidized and un-oxidized pressure-tube specimens has been measured at high temperatures under vacuum. The emissivity values of un-oxidized tube specimens decreased only slightly from 0.34 at 600 °C to 0.30 at 800 °C and changed gradually to 0.25 at 1000 °C. In comparison, the emissivity of pre-oxidized pressure-tube specimens decreased drastically from 0.70 at 600 °C to 0.35 at 800 °C, and gradually decreased to 0.25 at 1000 °C. The oxide layer of the pre-oxidized tube specimens dissolved into the metal matrix when heated to 700 °C and higher. Using these results, 2 linear correlations were obtained for emissivity with the oxide thickness measured by scanning electron microscopy and secondary ion mass spectroscopy analysis.

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“…During the phase transformation in polycrystalline aggregates, the so-called variant selection takes place which makes certain crystallographically equivalent variants fulfilling the Burgers orientation relationship more likely due to, for example, mechanical grain-grain interactions. The / phase transformation itself and the phenomenon of variant selection were also investigated using neutron diffraction for zirconium [82] and Zr-2.5Nb [83,84]. In order to predict the phase transformation texture, the variant selection has to be understood, which is a field of active research.…”

Section: Deformation Studiesmentioning

confidence: 99%

A Review of Neutron Scattering Applications to Nuclear Materials

Vogel

2013

ISRN Materials Science

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The growing demand for electric energy will require expansion of the amount of nuclear power production in many countries of the world. Research and development in this field will continue to grow to further increase safety and efficiency of nuclear power generation. Neutrons are a unique probe for a wide range of problems related to these efforts, ranging from crystal chemistry of nuclear fuels to engineering diffraction on cladding or structural materials used in nuclear reactors. Increased flux at modern neutron sources combined with advanced sample environments allows nowadays, for example, studies of reaction kinetics at operating temperatures in a nuclear reactor. Neutrons provide unique data to benchmark simulations and modeling of crystal structure evolution and thermomechanical treatment. Advances in neutron detection recently opened up new avenues of materials characterization using neutron imaging with unparalleled opportunities especially for nuclear materials, where heavy elements (e.g., uranium) need to be imaged together with light elements (e.g., hydrogen, oxygen). This paper summarizes applications of neutron scattering techniques for nuclear materials. Directions for future research, extending the trends observed over the past decade, are discussed.

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Crystallographic Texture and Volume Fraction of α and β Phases in Zr-2.5Nb Pressure Tube Material During Heating and Cooling

Cited by 25 publications

References 25 publications

Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr

Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr

TOTAL HEMISPHERICAL EMISSIVITY OF PRE-OXIDIZED AND UN-OXIDIZED ZR-2.5Nb PRESSURE-TUBE MATERIALS AT 600 °C TO 1000 °C UNDER VACUUM

A Review of Neutron Scattering Applications to Nuclear Materials

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