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Title: Evolution of extended defects in UO2 during high temperature annealing

Journal Article · · Journal of Nuclear Materials
 [1];  [2]; ORCiD logo [3]; ORCiD logo [2];  [4]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States); National Energy Technology Laboratory (NETL), Pittsburgh, PA, Morgantown, WV, and Albany, OR (United States)
  2. The Ohio State Univ., Columbus, OH (United States)
  3. North Carolina State University, Raleigh, NC (United States)
  4. Idaho National Laboratory (INL), Idaho Falls, ID (United States); North Carolina State University, Raleigh, NC (United States)

The evolution of thermophysical characteristics of uranium oxide (UO2) under irradiation is a critical aspect of nuclear fuel performance of light water reactors. This study examines the effect of high-temperature annealing at 1000 °C - 1600 °C on defect evolution in krypton irradiated UO2 at room temperature. Transmission electron microscopy analysis reveals that the size of irradiation-induced bubbles and dislocation loops increases but their density decreases with annealing temperatures. Perfect dislocation loops with = <110> dominate, regardless of the annealing temperature. A rate theory model for extended defect evolution is applied to conclude that current understanding of dynamical loop and bubble evolution at high-temperature annealing is governed by defect coalescence.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Science (SC), Basic Energy Sciences (BES)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2432419
Report Number(s):
INL/JOU--24-79881-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: - Vol. 593; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (52)

Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide journal November 2014
Thermal recovery of lattice defects in alpha-irradiated UO2 crystals journal February 1983
Consideration of swelling and thermodynamic stability of inert gas bubbles in solids journal October 1992
Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6–83 GWd/t journal November 1993
Microstructure evolution during irradiation journal October 1994
Dislocation and void formation in proton-bombarded and annealed gallium arsenide journal February 1983
Radiation-Induced Effects on Microstructure**Prepared for the Oak Ridge National Laboratory under Contract No. DE-AC05-000R22725 book February 2012
On the behaviour of intragranular fission gas in UO2 fuel journal June 2000
Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness journal November 2003
Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases journal June 1998
Direct observation of the coalescence process between nanoscale dislocation loops with different Burgers vectors journal January 2011
High temperature annealing of ion irradiated tungsten journal May 2015
Combining mesoscale thermal transport and x-ray diffraction measurements to characterize early-stage evolution of irradiation-induced defects in ceramics journal July 2020
Extended defect change in UO2 during in situ TEM annealing journal September 2020
Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation journal April 2021
An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide journal July 2021
Simulation study of helium bubble coalescence in tungsten at various temperatures relevant to fusion conditions journal February 2021
Re-solution of fission gas – A review: Part I. Intragranular bubbles journal August 2006
Modelling of grain face bubbles coalescence in irradiated UO2 fuel journal February 2008
Nuclear fuels – Present and future journal May 2009
Effects of edge dislocations on thermal transport in UO2 journal March 2013
Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation journal November 2014
Atomistic modeling of growth and coalescence of helium nano-bubbles in tungsten journal August 2015
Empirical potential simulations of interstitial dislocation loops in uranium dioxide journal October 2016
Evolution of extended defects in polycrystalline Au-irradiated UO 2 using in situ TEM: Temperature and fluence effects journal December 2016
Full characterization of dislocations in ion-irradiated polycrystalline UO2 journal October 2017
On the effect of irradiation-induced resolution in modelling fission gas release in UO 2 LWR fuel journal December 2017
Bubble evolution in Kr-irradiated UO2 during annealing journal December 2017
Unit mechanisms of fission gas release: Current understanding and future needs journal June 2018
Effect of fission generated defects and porosity on thermo-mechanical properties of thorium dioxide journal November 2018
Fission gas release from UO2 nuclear fuel: A review journal January 2019
Influence of exogenous xenon atoms on the evolution kinetics of extended defects in polycrystalline UO2 using in situ TEM journal December 2018
In-situ TEM observation of nanobubbles evolution in helium-irradiated aluminium upon tensile stressing journal July 2019
Impact of fission gas bubbles on thermal conductivity of UO2 fuels with high thermal conductivity additives journal April 2021
Insight into defect cluster annihilation at grain boundaries in an irradiated nanocrystalline iron journal August 2022
Influence of point defect accumulation on in-pile thermal conductivity degradation: Fuel rod defect distribution and deviation between in-pile and post irradiation thermal conductivity journal January 2023
Diffusion of Xe and Kr implanted at low concentrations in UO2 as a function of temperature – An experimental study journal August 2023
Local thickness measurement through scattering contrast and electron energy-loss spectroscopy journal January 2012
In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing journal August 2020
Indirect characterization of point defects in proton irradiated ceria journal March 2021
In situ characterization of irradiation-induced microstructural evolution in urania single crystals at 773 K journal November 2018
Gaseous swelling of U3Si2 during steady-state LWR operation: A rate theory investigation journal October 2017
Temperature effects on the radiation damage morphology in nanocrystalline iron journal May 2022
Electron energy loss spectroscopy investigation through a nano ablated uranium dioxide sample journal March 2013
Early stages of irradiation induced dislocations in urania journal October 2016
Alpha-irradiation damage in CeO 2 , UO 2 and PuO 2 journal January 1984
Radiation damage in uranium dioxide journal December 1965
Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO 2 Fuels journal September 1993
Mechanism of Formation and Growth of 〈 100 〉 Interstitial Loops in Ferritic Materials journal June 2002
Impact of irradiation induced dislocation loops on thermal conductivity in ceramics journal June 2019
Dislocation loop evolution in Kr‐irradiated ThO 2 journal April 2022
Effect of Radiation Defects on Thermo–Mechanical Properties of UO2 Investigated by Molecular Dynamics Method journal April 2022