FCRD Transmutation Fuels Handbook 2015

Janney, Dawn E.; Papesch, Cynthia A.

doi:10.2172/1239879

Cited by 7 publications

(5 citation statements)

References 109 publications

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“…Using energy-resolved neutron imaging, a U-20Pu-10Zr-3Np-2Am (weight percent) sample, an alloy researched for transmutation nuclear fuels [19], was characterized to obtain the bulk composition for comparison with mass-spectrometry. The sample consisted of a 20 mm long, 4.2 mm diameter U-20Pu-10Zr-3Np-2Am (weight percent) cast fuel slug contained in a double-walled steel container.…”

Section: Energy-resolved Neutron Imaging Of Nuclear Fuel Slugsmentioning

confidence: 99%

3D Isotope Density Measurements by Energy-Resolved Neutron Imaging

Losko

Vogel

2021

Preprint

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Tools for three-dimensional elemental characterization are available on length scales ranging from individual atoms, using electrons as a probe, to micrometers with X-rays. However, for larger volumes up to millimeters or centimeters, quantitative measurements of elemental or isotope densities were hitherto only possible on the surface. Here, a novel quantitative elemental characterization method based on energy-resolved neutron imaging, utilizing the known neutron absorption cross sections with their ‘finger-print’ absorption resonance signatures, is demonstrated. Enabled by a pixilated time-of-flight neutron transmission detector installed at an intense short-pulsed spallation neutron source, for this demonstration 3.25 million state-of-the-art nuclear physics neutron transmission analyses were conducted to derive isotopic densities for five isotopes in 3D in a volume of 0.25 cm3. The tomographic reconstruction of the isotope densities provides elemental maps similar to X-ray microprobe maps for any cross-section in the probed volume. The bulk isotopic density of a U-20Pu-10Zr-3Np-2Am nuclear transmutation fuel sample was measured, agrees well with mass-spectrometry and is evidence of the accuracy of the method.

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Section: Energy-resolved Neutron Imaging Of Nuclear Fuel Slugsmentioning

confidence: 99%

3D Isotope Density Measurements by Energy-Resolved Neutron Imaging

Losko

Vogel

2021

Preprint

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“…Extensive effort has been put forward in the generation of the metallic fuels handbooks, which contain some fundamental property data such as crystal structures, thermal expansion, phase diagrams, thermal conductivities and heat capacities on unirradiated fuels [39], [40]. This is incredibly valuable information, but is insufficient for the goal of developing improved, qualified metallic nuclear fuel for advanced reactors.…”

Section: Other Considerationsmentioning

confidence: 99%

Research Needs for Uranium-Zirconium- Based Metallic Fuels

Aitkaliyeva

Tonks

Hirschhorn

et al. 2020

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The purpose of this report is to summarize the needs and present recommendations related to the future direction for U-Zr-based metallic fuel research (including binary U-Zr and ternary U-Pu-Zr alloys). These needs and recommendations were determined by subject matter experts from various institutions during a two-day workshop held at the University of Florida in November, 2019. During open-floor discussions, the highest priority gaps in our understanding of U-Zr-based fuels were down-selected, and near-and long-term needs that directly impact the implementation of these metallic fuels were identified. The identified near-term needs include investigation of the following phenomena: i) swelling and fission gas release, ii) fuel-cladding chemical interaction, iii) phase evolution/constituent redistribution, and iv) thermal properties of the fuels. The long-term needs are: i) investigation of fuel creep and plasticity and ii) fission product (lanthanide) transport. In addition, there was general agreement that all institutions and subject matter experts would benefit from an open-source metallic fuels database with thermophysical property and microstructural data, along with fuel operation/irradiation history, which should be regularly updated with vetted information from new experimental and computational investigations and used to advance metallic fuels research and development. Finally, we recommend that metallic fuel research should be ongoing and that fuel qualification and fuel optimization should be equally prioritized; research combining experiments with modeling and simulation has the largest potential impact.

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“…This would tend to indicate that the underlying crystal structure of the fuel material is cubic everywhere except the outer 500 µm. The U-Pu-Zr ternary phase diagram [38] suggests that any of the DOE1 or AFC-1H R1, R4 fuel operating above 600°C should be a cubic (bcc) phase. This phase is γ-(U, Zr) and ε-Pu.…”

Section: Metallographymentioning

confidence: 99%

“…However, with the amount of porosity present, the typical porosity behavior of binary and ternary U-Zr and U-Pu-Zr alloys may not hold. In historic binary or ternary metallic fuels, lenticular pores can be formed at temperatures below the γ phase transition temperature (776°C) [38]. The cladding temperature of DOE1 was calculated to be approximately 550°C, so there should be a region of the fuel showing non-spherical porosity that was irradiated below the γ-U phase transition temperature [26].…”

Section: Metallographymentioning

confidence: 99%

Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

Harp

Capriotti

Hayes

et al. 2017

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The testing of fast reactor fuels in the thermal-spectrum of the Advanced Test Reactor using cadmium-filtering has been underway since 2003. The objective of this experimental approach to create a temperature profile inside of test fuel rodlets that is nearly prototypic of corresponding fast reactor conditions. This requires, necessarily, that the power generation profile inside of test fuel rodlets also be nearly prototypic of corresponding fast reactor conditions. By doing so, this experimental approach should allow for the study of fast reactor fuel performance phenomena that are primarily dependent upon the conditions of temperature and/or temperature gradient inside the fuel to be possible using a thermal test reactor. Validation of this assertion has been undertaken by both supporting analyses and by comparing fuel performance phenomena observed in fuels irradiated in cadmium-filtered positions in ATR to similar or identical fuels irradiated under similar conditions in genuine fast reactors. This report documents a preliminary comparison of fuel performance data available from the testing of metallic, oxide, and nitride fuels in cadmium-filtered positions in the ATR to the performance of identical or similar fuels irradiated in genuine fast reactors. Although a variety of fuel performance metrics are presented, particular attention is paid to those phenomena that are primarily, or significantly, dependent on conditions of temperature and temperature gradient with the fuel. Although the comparisons presented in this report are at this time limited in scope and preliminary in nature, they do support the assertion that the objectives of the cadmium-filtered testing approach in ATR are both feasible and appear sound. The analyses and comparisons presented in this report show that ATR irradiations performed using cadmium shrouding are sufficiently prototypic Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report vi

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FCRD Transmutation Fuels Handbook 2015

Cited by 7 publications

References 109 publications

3D Isotope Density Measurements by Energy-Resolved Neutron Imaging

3D Isotope Density Measurements by Energy-Resolved Neutron Imaging

Research Needs for Uranium-Zirconium- Based Metallic Fuels

Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

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