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Title: Bubble evolution in Kr-irradiated UO 2 during annealing

Abstract

Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO 2 annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average size 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 denude 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. Lastly, the area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.

Authors:
ORCiD logo [1];  [2];  [3]; ORCiD logo [4]; ORCiD logo [1]; ORCiD logo [5];  [6];  [7]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States). Dept. of Materials Science and Engineering
  3. Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)
  4. Boise State Univ., ID (United States). Dept. of Materials Science and Engineering
  5. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  6. Purdue Univ., West Lafayette, IN (United States). School of Materials Engineering
  7. Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineering Physics
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); USDOE Laboratory Directed Research and Development (LDRD) Program
OSTI Identifier:
1396012
Alternate Identifier(s):
OSTI ID: 1549233
Report Number(s):
INL/JOU-17-42658
Journal ID: ISSN 0022-3115; PII: S0022311514006163
Grant/Contract Number:  
AC07-05ID14517; 14-098; AC07-051D14517; NE0008279
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 496; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; fission gas bubble; irradiation; microstructure; nuclear fuel

Citation Formats

He, L., Bai, X. M., Pakarinen, J., Jaques, B. J., Gan, J., Nelson, A. T., El-Azab, A., and Allen, T. R. Bubble evolution in Kr-irradiated UO2 during annealing. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.09.036.
He, L., Bai, X. M., Pakarinen, J., Jaques, B. J., Gan, J., Nelson, A. T., El-Azab, A., & Allen, T. R. Bubble evolution in Kr-irradiated UO2 during annealing. United States. doi:10.1016/j.jnucmat.2017.09.036.
He, L., Bai, X. M., Pakarinen, J., Jaques, B. J., Gan, J., Nelson, A. T., El-Azab, A., and Allen, T. R. Wed . "Bubble evolution in Kr-irradiated UO2 during annealing". United States. doi:10.1016/j.jnucmat.2017.09.036. https://www.osti.gov/servlets/purl/1396012.
@article{osti_1396012,
title = {Bubble evolution in Kr-irradiated UO2 during annealing},
author = {He, L. and Bai, X. M. and Pakarinen, J. and Jaques, B. J. and Gan, J. and Nelson, A. T. and El-Azab, A. and Allen, T. R.},
abstractNote = {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 size 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 denude 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. Lastly, the area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries.},
doi = {10.1016/j.jnucmat.2017.09.036},
journal = {Journal of Nuclear Materials},
number = C,
volume = 496,
place = {United States},
year = {2017},
month = {9}
}

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