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Title: Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel

Abstract

Phase-stability in a U-Zr-Te-Nd multi-component metallic fuel for advanced nuclear reactors is systematically investigated by taking into account binary, ternary and quaternary interactions between elements involved. Historically, the onset of fuel-cladding chemical interactions (FCCI) greatly limits the burnup potential of U-Zr fuels primarily due to interactions between lanthanide fission products and cladding constituents. Tellurium (Te) is evaluated as a potential additive for U-Zr fuels to bind with lanthanide fission products, e.g. neodymium (Nd), negating or mitigating the FCCI effect. Potential fresh fuel alloy compositions with the Te additive, U-Zr-Te, are characterized. Te is found to completely bind with Zr within the U-Zr matrix. Alloys simulating the formation of the lanthanide element Nd within U-Zr-Te are also evaluated, where the Te-Nd binary interaction dominates and NdTe is found to form as a high temperature stable compound. The experimental observations agree well with the trends obtained from density functional theory calculations. According to the calculated enthalpy of mixing, Zr-Te compound formation is favored in the U-Zr-Te alloy whereas NdTe compound formation is favored in the U-Zr-Te-Nd alloy. Further, the calculated charge density distribution and density of states provide sound understanding of the mutual chemical interactions between elements and phase-stability within the multi-componentmore » fuel.« less

Authors:
ORCiD logo [1];  [2]; ORCiD logo [3]; ORCiD logo [3]; ORCiD logo [3];  [4];  [4];  [2];  [2]; ORCiD logo [5]
  1. Univ. of Idaho, Moscow, ID (United States). Dept. of Chemical and Materials Engineering; Idaho National Lab. (INL), Idaho Falls, ID (United States). Materials and Fuels Complex Div.
  2. Univ. of Idaho, Moscow, ID (United States). Dept. of Chemical and Materials Engineering
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States). Materials and Fuels Complex Div.
  4. Center for Advanced Energy Studies, Idaho Falls, ID (United States). Microscopy and Characterization Suite
  5. Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Div.
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States); Univ. of Idaho, Moscow, ID (United States)
Sponsoring Org.:
USDOE Nuclear Energy University Program (NEUP); USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1574008
Alternate Identifier(s):
OSTI ID: 1575109
Report Number(s):
INL/JOU-19-53651-Rev001
Journal ID: ISSN 2045-2322
Grant/Contract Number:  
AC07-05ID14517; NE0008557
Resource Type:
Accepted Manuscript
Journal Name:
Scientific Reports
Additional Journal Information:
Journal Volume: 9; Journal Issue: 1; Journal ID: ISSN 2045-2322
Publisher:
Nature Publishing Group
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; Fuel Additive; Metallic Fuel; U-10Zr; Pellet Cladding Interaction (PCI); Fuel Cladding Chemical Interaction (FCCI); fuel-Cladding Chemical Interactions; dopant; fast reactor fuel

Citation Formats

Jerred, Nathan D., Khanal, Rabi, Benson, Michael T., Perez, Emmanuel Enrrique, King, James A., Dubey, Megha, Burns, Jatuporn, Charit, Indrajit, Choudhury, Samrat, and Mariani, Robert D. Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel. United States: N. p., 2019. Web. doi:10.1038/s41598-019-51852-z.
Jerred, Nathan D., Khanal, Rabi, Benson, Michael T., Perez, Emmanuel Enrrique, King, James A., Dubey, Megha, Burns, Jatuporn, Charit, Indrajit, Choudhury, Samrat, & Mariani, Robert D. Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel. United States. doi:10.1038/s41598-019-51852-z.
Jerred, Nathan D., Khanal, Rabi, Benson, Michael T., Perez, Emmanuel Enrrique, King, James A., Dubey, Megha, Burns, Jatuporn, Charit, Indrajit, Choudhury, Samrat, and Mariani, Robert D. Tue . "Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel". United States. doi:10.1038/s41598-019-51852-z. https://www.osti.gov/servlets/purl/1574008.
@article{osti_1574008,
title = {Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel},
author = {Jerred, Nathan D. and Khanal, Rabi and Benson, Michael T. and Perez, Emmanuel Enrrique and King, James A. and Dubey, Megha and Burns, Jatuporn and Charit, Indrajit and Choudhury, Samrat and Mariani, Robert D.},
abstractNote = {Phase-stability in a U-Zr-Te-Nd multi-component metallic fuel for advanced nuclear reactors is systematically investigated by taking into account binary, ternary and quaternary interactions between elements involved. Historically, the onset of fuel-cladding chemical interactions (FCCI) greatly limits the burnup potential of U-Zr fuels primarily due to interactions between lanthanide fission products and cladding constituents. Tellurium (Te) is evaluated as a potential additive for U-Zr fuels to bind with lanthanide fission products, e.g. neodymium (Nd), negating or mitigating the FCCI effect. Potential fresh fuel alloy compositions with the Te additive, U-Zr-Te, are characterized. Te is found to completely bind with Zr within the U-Zr matrix. Alloys simulating the formation of the lanthanide element Nd within U-Zr-Te are also evaluated, where the Te-Nd binary interaction dominates and NdTe is found to form as a high temperature stable compound. The experimental observations agree well with the trends obtained from density functional theory calculations. According to the calculated enthalpy of mixing, Zr-Te compound formation is favored in the U-Zr-Te alloy whereas NdTe compound formation is favored in the U-Zr-Te-Nd alloy. Further, the calculated charge density distribution and density of states provide sound understanding of the mutual chemical interactions between elements and phase-stability within the multi-component fuel.},
doi = {10.1038/s41598-019-51852-z},
journal = {Scientific Reports},
number = 1,
volume = 9,
place = {United States},
year = {2019},
month = {11}
}

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