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:

Jerred, Nathan D.  ^[1];

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• Search DOE PAGES for ORCID "0000-0003-2887-639X"

Khanal, Rabi ^[2]; Benson, Michael T.  ^[3];

• Search DOE PAGES for author "Benson, Michael T."
• Search DOE PAGES for ORCID "0000-0003-4927-614X"

Perez, Emmanuel  ^[3];

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• Search DOE PAGES for ORCID "0000-0001-5546-4978"

King, James A.  ^[3];

• Search DOE PAGES for author "King, James A."
• Search DOE PAGES for ORCID "0000-0003-3728-4759"

Dubey, Megha ^[4]; Burns, Jatuporn ^[4]; Charit, Indrajit ^[2]; Choudhury, Samrat ^[2]; Mariani, Robert D.  ^[5]

• Search DOE PAGES for author "Mariani, Robert D."
• Search DOE PAGES for ORCID "0000-0002-7502-3536"

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+ Show Author Affiliations

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:

Tue Nov 05 00:00:00 EST 2019

Research Org.:

Univ. of Idaho, Moscow, ID (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Org.:

USDOE Office of Nuclear Energy (NE); USDOE Nuclear Energy University Program (NEUP)

OSTI Identifier:

1575108

Alternate Identifier(s):

OSTI ID: 1574008

Report Number(s):

INL/JOU-19-53651-Rev001
Journal ID: ISSN 2045-2322; CFDA # 81.121; TRN: US2100313

Grant/Contract Number:  

NE0008557; AC07-05ID14517

Resource Type:

Accepted Manuscript

Journal Name:

Scientific Reports

Additional Journal Information:

Journal Volume: 9; Journal Issue: 1; Related Information: None; Journal ID: ISSN 2045-2322

Publisher:

Nature Publishing Group

Country of Publication:

United States

Language:

English

Subject:

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Fuel Additive; Metallic Fuel; U-10Zr; Pellet Cladding Interaction (PCI); Fuel Cladding Chemical Interaction (FCCI); 36 MATERIALS SCIENCE