4.7 Article

Recent trends in metallic fast reactor fuels research

相关参考文献

注意:仅列出部分参考文献,下载原文获取全部文献信息。
Article Materials Science, Multidisciplinary

Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding

Xiang Liu et al.

Summary: The annular metallic fuel design eliminates the liquid sodium bond between the fuel and the cladding, providing back-end fuel cycle and other benefits, presenting new features. Negligible amounts of lanthanides were found in the FCCI layer in the investigated annular fuel, with most retained in the newly formed UZr 2 phase in the fuel center region.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Evaluation of the anisotropic grain boundaries and surfaces of α-U via molecular dynamics

Khadija Mahbuba et al.

Summary: This study evaluates the grain boundary, surface energy, and work of adhesion of alpha-U using molecular dynamics, and analyzes the effect of temperature, tilt plane, and misorientation angle on interfacial energies. The research provides important theoretical support for the application of metallic fuels in reactors.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products

Max Poschmann et al.

Summary: A new formulation for redistribution of constituents in metallic U-Pu-Zr nuclear fuel has been presented, which incorporates the contributions from fission products and is based on thermodynamic driving forces. The simulations show that the generation of fission products during burnup stabilizes the fuel chemistry.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content

Thaddeus Rahn et al.

Summary: This study investigated fuel constituent segregation and fuel-cladding chemical interactions in three U-Pu-Zr fuel pins irradiated in Experimental Breeder Reactor-II. Optical and SEM results showed that variation in Zr content alters the number and size of constituent redistribution zones in the fuel, with all examined fuels having four or more distinct redistribution regions. This complexity highlights the need for further studies using advanced instrumentation.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient

Fidelma G. Di Lemma et al.

Summary: This study investigated the influence of a reactor overpower transient on irradiated metallic fuel performance and demonstrated that a moderate transient did not significantly affect fuel performance.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON

Jacob Hirschhorn et al.

Summary: A CALPHAD-informed constituent redistribution model was developed and incorporated into the BISON fuel performance code, calibrated with three uncertain model parameters to accurately predict the behavior of U-Zr fuels. Model predictions for U-Pu-Zr fuels were less accurate, with potential improvement by reducing uncertainties in ternary phase transition temperatures and collecting more kinetic data. The new model was successfully coupled with existing thermomechanics models to accurately simulate irradiation of U-Zr fuels at the engineering scale.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Microstructure Evolution of U-Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U-10Zr (wt. %)

Yi Xie et al.

Summary: The microstructure evolution of 1073K extruded U-10Zr fuel during thermal cycling was investigated using in situ neutron diffraction. The alpha-U phase exhibits lattice contraction in the b direction and lattice expansion in other directions with increasing temperature, while other phases exhibit lattice expansion in all directions with temperature. Contrary to the established phase diagram, the beta-U phase is absent during the thermal cycling.

JOURNAL OF NUCLEAR MATERIALS (2021)

Review Nuclear Science & Technology

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

G. L. Beausoleil et al.

Summary: With the growing interest in sodium fast reactor technology, an accelerated fuel qualification method is needed. An analysis was performed to identify priority parameters for a U-Pu-Zr sodium-free annular fuel system, which were then reviewed against existing capabilities to support investigation of the highest-priority parameters. A pathway for qualification was established utilizing high-throughput, high-volume experiments and advanced physics-based model development.

NUCLEAR TECHNOLOGY (2021)

Article Materials Science, Multidisciplinary

Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment

Ian Greenquist et al.

Summary: Metallic nuclear fuels are being researched and developed for use in advanced reactors. A benchmark case based on the IFR-1 experiment was developed to assess the accuracy of existing metallic fuel performance models. The results showed reasonably accurate predictions for burnup and fission gas release, but errors in temperature and dimensional change predictions. Further development should focus on cladding swelling behaviors to improve dimensional change predictions.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound

A. Khanolkar et al.

Summary: The study used laser-generated ultrasound to monitor microstructure evolution in different compositions of polycrystalline binary uranium-zirconium metallic fuel alloys during thermal processing. The findings revealed unique ultrasonic responses and structural evolution characteristics at different temperatures in the alloys. Ultrasonic measurements and in situ transmission electron microscopy images showed nanoscale and micron-scale structure evolution in the alloys under various thermal conditions.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Behavior of metallic fast reactor fuels during an overpower transient

Daniel M. Wachs et al.

Summary: This study conducted an extended overpower transient test on metallic alloy fuel elements in EBR-II, demonstrating that limits on sodium fast reactor operational transients could be applied with adequate safety margins. Fuel pins maintained cladding integrity throughout normal operation and overpower transient tests. The post-irradiation examination showed mild restructuring within the fuel phase, but not significant enough to impact irradiation performance under normal operating conditions if the fuel elements were returned to service.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences

Jason M. Harp et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Reexamination of a U-Zr diffusion couple experiment using quantitative phase-field modeling and sensitivity analysis

Jacob Hirschhorn et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Intragranular thermal transport in U-50Zr

Zilong Hua et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II

Luca Capriotti et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels

H. J. M. Chichester et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Investigation of the microstructure evolution of alpha uranium after in pile transient

Fidelma G. Di Lemma et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Molar heat capacity of uranium-rich U-Zr-Nb and U-Zr-Mo alloys

Santu Kaity et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Nd, SbNd and Sb3Nd4 and their interactions with the cladding alloy HT9

Nathan D. Jerred et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel

Tiankai Yao et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Atomistic calculations of the surface energy as a function of composition and temperature in γ U-Zr to inform fuel performance modeling

Benjamin Beeler et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels

Rabi Khanal et al.

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

On spinodal-like phase decomposition in U-50Zr alloy

Tiankai Yao et al.

MATERIALIA (2020)

Review Materials Science, Multidisciplinary

Fuel cladding chemical interaction in metallic sodium fast reactor fuels: A historical perspective

Dennis D. Keiser

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Nuclear Science & Technology

Development and verification of a phase-field model for the equilibrium thermodynamics of U-Pu-Zr

Jacob Hirschhorn et al.

ANNALS OF NUCLEAR ENERGY (2019)

Article Materials Science, Multidisciplinary

Postirradiation Examination of FUTURIX-FTA metallic alloy experiments

Jason M. Harp et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Theoretical study on stability, mechanical and thermodynamic properties of (Pu, Zr)N

Yujuan Zhang et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

A study of constituent redistribution in U-Zr fuels using quantitative phase-field modeling and sensitivity analysis

Jacob Hirschhorn et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

An Estimation of the Thermal Properties of Pu-Rich Metallic Fuel

Naoya Odaira et al.

ADVANCES IN MATERIALS SCIENCE AND ENGINEERING (2019)

Article Materials Science, Multidisciplinary

Shear strength of nanocrystalline δ-phase Pu-Ga alloys: Atomistic simulations

A. Karavaev et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Diffusion behaviors between metallic fuel alloys with Pd addition and Fe

Yi Xie et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Studies on fuel-cladding chemical interaction between U-10 wt%Zr alloy and T91 steel

Santu Kaity et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Assessment of Te as a U-Zr fuel additive to mitigate fuel-cladding chemical interactions

Yi Xie et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Defect production and segregation induced by collision cascades in U-10Zr alloy

Ning Zhou et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with added minor actinides

Karen E. Wright et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Temperature and composition dependent thermal conductivity model for U-Zr alloys

Weiming Chen et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides

Yi Xie et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations

Jason M. Harp et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Postirradiation examination on metallic fuel in the AFC-2 irradiation test series

Jason M. Harp et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Calculation of the displacement energy of α and γ uranium

Benjamin Beeler et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn plus Sb as a mixed additive system to bind lanthanides

Michael T. Benson et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Simulated Microstructural and Compositional Evolution of U-Pu-Zr Alloys Using the Potts-Phase Field Modeling Technique

Jordan J. Cox et al.

METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE (2018)

Article Materials Science, Multidisciplinary

Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9

Jason M. Harp et al.

JOURNAL OF NUCLEAR MATERIALS (2017)

Review Nuclear Science & Technology

Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review

Christopher Matthews et al.

NUCLEAR TECHNOLOGY (2017)

Article Nuclear Science & Technology

Characterization of metallic fuel for minor actinides transmutation in fast reactor

L. Capriotti et al.

PROGRESS IN NUCLEAR ENERGY (2017)

Article Nuclear Science & Technology

A Summary of the Department of Energy's Advanced Demonstration and Test Reactor Options Study

D. Petti et al.

NUCLEAR TECHNOLOGY (2017)

Article Materials Science, Multidisciplinary

Metallic fuels for advanced reactors

W. J. Carmack et al.

JOURNAL OF NUCLEAR MATERIALS (2009)