Bubble Evolution in Kr-Irradiated UO2 During Annealing

L. He; X. M. Bai; J. Pakarinen; B. J. Jaques; J. Gan; A. T. Nelson; A. El-Azab; T. R. Allen

doi:10.1016/j.jnucmat.2017.09.036

Bubble Evolution in Kr-Irradiated UO₂ During Annealing

L. He, X. M. Bai, J. Pakarinen, B. J. Jaques, J. Gan, A. T. Nelson, A. El-Azab, T. R. Allen

Micron School of Materials Science and Engineering

Research output: Contribution to journal › Article › peer-review

15 Scopus citations

Abstract

Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO₂ annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average diameter of intragranular bubbles increased gradually from 0.8 nm in as-irradiated sample at room temperature to 2.6 nm at 1600 °C and the bubble size distribution changed from a uniform distribution to a bimodal distribution above 1300 °C. The size of intergranular bubbles increased more rapidly than intragranular ones and bubble denuded zones near grain boundaries formed in all the annealed samples. It was found that high-angle grain boundaries held bigger bubbles than low-angle grain boundaries. Complementary atomistic modeling was conducted to interpret the effects of grain boundary character on the Kr segregation. The area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.

Original language	American English
Pages (from-to)	242-250
Number of pages	9
Journal	Journal of Nuclear Materials
Volume	496
DOIs	https://doi.org/10.1016/j.jnucmat.2017.09.036
State	Published - 1 Dec 2017

EGS Disciplines

Materials Science and Engineering

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10.1016/j.jnucmat.2017.09.036

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title = "Bubble Evolution in Kr-Irradiated UO2 During Annealing",

abstract = "Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO2 annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average diameter of intragranular bubbles increased gradually from 0.8 nm in as-irradiated sample at room temperature to 2.6 nm at 1600 °C and the bubble size distribution changed from a uniform distribution to a bimodal distribution above 1300 °C. The size of intergranular bubbles increased more rapidly than intragranular ones and bubble denuded zones near grain boundaries formed in all the annealed samples. It was found that high-angle grain boundaries held bigger bubbles than low-angle grain boundaries. Complementary atomistic modeling was conducted to interpret the effects of grain boundary character on the Kr segregation. The area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.",

author = "L. He and Bai, {X. M.} and J. Pakarinen and Jaques, {B. J.} and J. Gan and Nelson, {A. T.} and A. El-Azab and Allen, {T. R.}",

note = "Publisher Copyright: {\textcopyright} 2017",

year = "2017",

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doi = "10.1016/j.jnucmat.2017.09.036",

language = "American English",

volume = "496",

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TY - JOUR

T1 - Bubble Evolution in Kr-Irradiated UO2 During Annealing

AU - He, L.

AU - Bai, X. M.

AU - Pakarinen, J.

AU - Jaques, B. J.

AU - Gan, J.

AU - Nelson, A. T.

AU - El-Azab, A.

AU - Allen, T. R.

PY - 2017/12/1

Y1 - 2017/12/1

N2 - Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO2 annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average diameter of intragranular bubbles increased gradually from 0.8 nm in as-irradiated sample at room temperature to 2.6 nm at 1600 °C and the bubble size distribution changed from a uniform distribution to a bimodal distribution above 1300 °C. The size of intergranular bubbles increased more rapidly than intragranular ones and bubble denuded zones near grain boundaries formed in all the annealed samples. It was found that high-angle grain boundaries held bigger bubbles than low-angle grain boundaries. Complementary atomistic modeling was conducted to interpret the effects of grain boundary character on the Kr segregation. The area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.

AB - Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO2 annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average diameter of intragranular bubbles increased gradually from 0.8 nm in as-irradiated sample at room temperature to 2.6 nm at 1600 °C and the bubble size distribution changed from a uniform distribution to a bimodal distribution above 1300 °C. The size of intergranular bubbles increased more rapidly than intragranular ones and bubble denuded zones near grain boundaries formed in all the annealed samples. It was found that high-angle grain boundaries held bigger bubbles than low-angle grain boundaries. Complementary atomistic modeling was conducted to interpret the effects of grain boundary character on the Kr segregation. The area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.

UR - http://www.scopus.com/inward/record.url?scp=85030677335&partnerID=8YFLogxK

UR - https://scholarworks.boisestate.edu/mse_facpubs/330

U2 - 10.1016/j.jnucmat.2017.09.036

DO - 10.1016/j.jnucmat.2017.09.036

M3 - Article

SN - 0022-3115

VL - 496

SP - 242

EP - 250

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Bubble Evolution in Kr-Irradiated UO₂ During Annealing

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