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Title: TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy

Abstract

As an essential part of global nuclear non-proliferation effort, the RERTR program is developing low enriched U-Mo fuels (< 20% U-235) for use in research and test reactors that currently employ highly enriched uranium fuels. One type of fuel being developed is a dispersion fuel plate comprised of U-7Mo particles dispersed in Al alloy matrix. Recent TEM characterizations of the ATR irradiated U-7Mo dispersion fuel plates include the samples with a local fission densities of 4.5, 5.2, 5.6 and 6.3 E+21 fissions/cm3 and irradiation temperatures of 101-136?C. The development of the irradiated microstructure of the U-7Mo fuel particles consists of fission gas bubble superlattice, large gas bubbles, solid fission product precipitates and their association to the large gas bubbles, grain subdivision to tens or hundreds of nanometer size, collapse of bubble superlattice, and amorphisation. This presentation will describe the observed microstructures specifically focusing on the U-7Mo fuel particles. The impact of the observed microstructure on the fuel performance and the comparison of the relevant features with that of the high burn-up UO2 fuels will be discussed.

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NA
OSTI Identifier:
1148997
Report Number(s):
INL/CON-13-30688
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: Research Reactor Fuel management (RRFM) 2014,Ljubljana, Slovenia,03/30/2014,04/03/2014
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Characterization; High burn-up; microstructure; TEM; U-7Mo

Citation Formats

Gan, Jian, Miller, Brandon, Keiser, Dennis, Robinson, Adam, Madden, James, Medvedev, Pavel, and Wachs, Daniel. TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy. United States: N. p., 2014. Web.
Gan, Jian, Miller, Brandon, Keiser, Dennis, Robinson, Adam, Madden, James, Medvedev, Pavel, & Wachs, Daniel. TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy. United States.
Gan, Jian, Miller, Brandon, Keiser, Dennis, Robinson, Adam, Madden, James, Medvedev, Pavel, and Wachs, Daniel. Tue . "TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy". United States. https://www.osti.gov/servlets/purl/1148997.
@article{osti_1148997,
title = {TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy},
author = {Gan, Jian and Miller, Brandon and Keiser, Dennis and Robinson, Adam and Madden, James and Medvedev, Pavel and Wachs, Daniel},
abstractNote = {As an essential part of global nuclear non-proliferation effort, the RERTR program is developing low enriched U-Mo fuels (< 20% U-235) for use in research and test reactors that currently employ highly enriched uranium fuels. One type of fuel being developed is a dispersion fuel plate comprised of U-7Mo particles dispersed in Al alloy matrix. Recent TEM characterizations of the ATR irradiated U-7Mo dispersion fuel plates include the samples with a local fission densities of 4.5, 5.2, 5.6 and 6.3 E+21 fissions/cm3 and irradiation temperatures of 101-136?C. The development of the irradiated microstructure of the U-7Mo fuel particles consists of fission gas bubble superlattice, large gas bubbles, solid fission product precipitates and their association to the large gas bubbles, grain subdivision to tens or hundreds of nanometer size, collapse of bubble superlattice, and amorphisation. This presentation will describe the observed microstructures specifically focusing on the U-7Mo fuel particles. The impact of the observed microstructure on the fuel performance and the comparison of the relevant features with that of the high burn-up UO2 fuels will be discussed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2014},
month = {4}
}

Conference:
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