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Title: Microstructure changes caused by annealing of U-Pu-Zr alloys

Authors:
;
Publication Date:
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1419384
Grant/Contract Number:
AC07-05ID14517
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 486; Journal Issue: C; Related Information: CHORUS Timestamp: 2018-02-02 14:38:05; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Janney, Dawn E., and Sencer, Bulent H. Microstructure changes caused by annealing of U-Pu-Zr alloys. Netherlands: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.01.003.
Janney, Dawn E., & Sencer, Bulent H. Microstructure changes caused by annealing of U-Pu-Zr alloys. Netherlands. doi:10.1016/j.jnucmat.2017.01.003.
Janney, Dawn E., and Sencer, Bulent H. Sat . "Microstructure changes caused by annealing of U-Pu-Zr alloys". Netherlands. doi:10.1016/j.jnucmat.2017.01.003.
@article{osti_1419384,
title = {Microstructure changes caused by annealing of U-Pu-Zr alloys},
author = {Janney, Dawn E. and Sencer, Bulent H.},
abstractNote = {},
doi = {10.1016/j.jnucmat.2017.01.003},
journal = {Journal of Nuclear Materials},
number = C,
volume = 486,
place = {Netherlands},
year = {Sat Apr 01 00:00:00 EDT 2017},
month = {Sat Apr 01 00:00:00 EDT 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.jnucmat.2017.01.003

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  • Density-functional theory, previously used to describe phase equilibria in the U-Zr alloys [1], is applied to study ground state properties of the bcc U-Pu-Zr solid solutions. Calculated heats of formation of the Pu-U and Pu-Zr alloys are in a good agreement with CALPHAD assessments. We found that account for spin-orbit coupling is important for successful description of Pu-containing alloys.
  • Metallic fuel alloys consisting of uranium, plutonium, and zirconium with minor additions of americium and neptunium are under evaluation for potential use to transmute long-lived transuranic actinide isotopes in fast reactors. A series of test designs for the Advanced Fuel Cycle Initiative (AFCI) have been irradiated in the Advanced Test Reactor (ATR), designated as the AFC-1 and AFC-2 designs. Metal fuel compositions in these designs have included varying amounts of U, Pu, Zr, and minor actinides (Am, Np). Investigations into the phase behavior and relationships based on the alloy constituents have been conducted using x-ray diffraction and differential thermal analysis.more » Results of these investigations, along with proposed relationships between observed behavior and alloy composition, are provided. In general, observed behaviors can be predicted by a ternary U-Pu-Zr phase diagram, with transition temperatures being most dependent on U content. Furthermore, the enthalpy associated with transitions is strongly dependent on the as-cast microstructural characteristics.« less
  • Computational simulations of gravity casting processes for metallic U–Pu–Zr nuclear fuel rods have been performed using a design-of-experiments technique to determine the fluid flow, liquid heat transfer, and solid heat transfer parameters which most strongly influence the process solidification speed and fuel rod porosity. The results are used to make recommendations for the best investment of experimental time and effort to measure process parameters.