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Title: Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results

Abstract

ABSTRACT Uranium-molybdenum (U-Mo) and uranium-zirconium (U-Zr) are two promising fuel candidates for nuclear transmutation reactors which burn long-lived minor actinides and fission products within fast spectrum reactors. The objectives of this research are centered on understanding the early stages of fuel performance through the examination of the irradiation induced microstructural changes in U-Zr and U-Mo alloys subjected to low neutron fluences. Specimens that were analyzed include those that were previously irradiated in the Advanced Test Reactor at INL. This most recent work has focused on a sub-set of the irradiated specimens, specifically U-Zr and U-Mo alloys that were irradiated to 0.01 dpa at temperatures ranging from (150-800oC). These specimens were analyzed with two types of synchrotron techniques, including X-ray absorption fine structure and X-ray diffraction. These techniques provide non-destructive microstructural analysis, including phase identification and quantitation, lattice parameters, crystallite sizes, as well as bonding, structure, and chemistry. Preliminary research has shown changes in the phase fractions, crystallite sizes, and lattice parameters as a function of irradiation and temperature. Future data analyses will continue to explore these microstructural changes.

Authors:
 [1];  [1];  [1];  [1];  [1];  [2];  [2];  [2];  [3];  [3];  [3]
  1. Purdue Univ., West Lafayette, IN (United States)
  2. Illinois Inst. of Technology, Chicago, IL (United States)
  3. Brookhaven National Lab. (BNL), Upton, NY (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1364512
Report Number(s):
INL/EXT-16-40130
TRN: US1703350
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; URANIUM; MOLYBDENUM; ZIRCONIUM; ALLOYS; FUELS; PERFORMANCE; Modeling Results; Report on the Synchrotron Characterization; U-Mo and U-Zr Alloys

Citation Formats

Okuniewski, Maria A., Ganapathy, Varsha, Hamilton, Brenden, Cassutt, Paul, Zhang, Fan, Velaquez, Daniel, Seibert, Rachel, Terry, Jeff, Sprouster, David, Ecker, Lynne, and Elbakhshwan, Mohamed. Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results. United States: N. p., 2016. Web. doi:10.2172/1364512.
Okuniewski, Maria A., Ganapathy, Varsha, Hamilton, Brenden, Cassutt, Paul, Zhang, Fan, Velaquez, Daniel, Seibert, Rachel, Terry, Jeff, Sprouster, David, Ecker, Lynne, & Elbakhshwan, Mohamed. Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results. United States. doi:10.2172/1364512.
Okuniewski, Maria A., Ganapathy, Varsha, Hamilton, Brenden, Cassutt, Paul, Zhang, Fan, Velaquez, Daniel, Seibert, Rachel, Terry, Jeff, Sprouster, David, Ecker, Lynne, and Elbakhshwan, Mohamed. Thu . "Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results". United States. doi:10.2172/1364512. https://www.osti.gov/servlets/purl/1364512.
@article{osti_1364512,
title = {Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results},
author = {Okuniewski, Maria A. and Ganapathy, Varsha and Hamilton, Brenden and Cassutt, Paul and Zhang, Fan and Velaquez, Daniel and Seibert, Rachel and Terry, Jeff and Sprouster, David and Ecker, Lynne and Elbakhshwan, Mohamed},
abstractNote = {ABSTRACT Uranium-molybdenum (U-Mo) and uranium-zirconium (U-Zr) are two promising fuel candidates for nuclear transmutation reactors which burn long-lived minor actinides and fission products within fast spectrum reactors. The objectives of this research are centered on understanding the early stages of fuel performance through the examination of the irradiation induced microstructural changes in U-Zr and U-Mo alloys subjected to low neutron fluences. Specimens that were analyzed include those that were previously irradiated in the Advanced Test Reactor at INL. This most recent work has focused on a sub-set of the irradiated specimens, specifically U-Zr and U-Mo alloys that were irradiated to 0.01 dpa at temperatures ranging from (150-800oC). These specimens were analyzed with two types of synchrotron techniques, including X-ray absorption fine structure and X-ray diffraction. These techniques provide non-destructive microstructural analysis, including phase identification and quantitation, lattice parameters, crystallite sizes, as well as bonding, structure, and chemistry. Preliminary research has shown changes in the phase fractions, crystallite sizes, and lattice parameters as a function of irradiation and temperature. Future data analyses will continue to explore these microstructural changes.},
doi = {10.2172/1364512},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {9}
}

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