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Title: Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation

Abstract

The effectiveness of a transition metal coating layer as a diffusion barrier between the UMo and matrix Al was examined. The samples were cut from KAERI-made U-Mo/Al dispersion miniplates containing 8 gU/cm3 fuel meat. Mo, W and Zr were included as coating candidates. A physical vapor deposition (PVD) method was used to produce about a 0.2-mu m thick coating layer on the UMo. An Al protection coating layer was subsequently applied to protect the main coating layer. The samples were irradiated at the ATLAS facility in Argonne National laboratory with 84-MeV Xe26+ ions, with the beam current of 200 particles nano ampere (pnA), to achieve a final dose of 2.7x1017 ions/cm2. Post-irradiation examinations included focused ion beam (FIB), scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS). Furthermore, among the coating metals, Mo showed the highest survival during the fuel plate fabrication and endurance during irradiation, which was consistent with the pre-irradiation thermodynamics evaluation. This result also emphasized the importance of the Al protection layer.

Authors:
 [1];  [2];  [1];  [2];  [2];  [2];  [2];  [2];  [1];  [1];  [1];  [2]
  1. Korea Atomic Energy Research Inst., Daejeon (South Korea)
  2. Argonne National Lab. (ANL), Lemont, IL (United States)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA); Ministry of Science, Information, and Future Planning (MSIP) of Korea
OSTI Identifier:
1606404
Alternate Identifier(s):
OSTI ID: 1578121
Grant/Contract Number:  
AC02-06CH11357; 2013M2A8A104241; AC-02-06CH11357
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 529; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; research reactor fuel, U-Mo dispersion fuel, ion radiation, coating method

Citation Formats

Kim, Sunghwan, Kim, Yeon Soo, Jeong, Y. J., Mo, K., Miao, Y., Ye, B., Oaks, A., Bhattacharya, S., Lee, K. H., Kim, K. N., Park, J. M., and Yacout, A. M.. Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation. United States: N. p., 2019. Web. https://doi.org/10.1016/j.jnucmat.2019.151945.
Kim, Sunghwan, Kim, Yeon Soo, Jeong, Y. J., Mo, K., Miao, Y., Ye, B., Oaks, A., Bhattacharya, S., Lee, K. H., Kim, K. N., Park, J. M., & Yacout, A. M.. Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation. United States. https://doi.org/10.1016/j.jnucmat.2019.151945
Kim, Sunghwan, Kim, Yeon Soo, Jeong, Y. J., Mo, K., Miao, Y., Ye, B., Oaks, A., Bhattacharya, S., Lee, K. H., Kim, K. N., Park, J. M., and Yacout, A. M.. Fri . "Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation". United States. https://doi.org/10.1016/j.jnucmat.2019.151945. https://www.osti.gov/servlets/purl/1606404.
@article{osti_1606404,
title = {Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation},
author = {Kim, Sunghwan and Kim, Yeon Soo and Jeong, Y. J. and Mo, K. and Miao, Y. and Ye, B. and Oaks, A. and Bhattacharya, S. and Lee, K. H. and Kim, K. N. and Park, J. M. and Yacout, A. M.},
abstractNote = {The effectiveness of a transition metal coating layer as a diffusion barrier between the UMo and matrix Al was examined. The samples were cut from KAERI-made U-Mo/Al dispersion miniplates containing 8 gU/cm3 fuel meat. Mo, W and Zr were included as coating candidates. A physical vapor deposition (PVD) method was used to produce about a 0.2-mu m thick coating layer on the UMo. An Al protection coating layer was subsequently applied to protect the main coating layer. The samples were irradiated at the ATLAS facility in Argonne National laboratory with 84-MeV Xe26+ ions, with the beam current of 200 particles nano ampere (pnA), to achieve a final dose of 2.7x1017 ions/cm2. Post-irradiation examinations included focused ion beam (FIB), scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS). Furthermore, among the coating metals, Mo showed the highest survival during the fuel plate fabrication and endurance during irradiation, which was consistent with the pre-irradiation thermodynamics evaluation. This result also emphasized the importance of the Al protection layer.},
doi = {10.1016/j.jnucmat.2019.151945},
journal = {Journal of Nuclear Materials},
number = ,
volume = 529,
place = {United States},
year = {2019},
month = {12}
}

Works referenced in this record:

Irradiation behavior of low-enriched U6Fe-Ai dispersion fuel elements
journal, October 1987


Development of very-high-density low-enriched-uranium fuels
journal, December 1997


Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002


Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel
journal, April 2008


Effect of Si and Zr on the interdiffusion of U–Mo alloy and Al
journal, March 2008


Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix
journal, May 2011


The Effect of Si-Rich Layer Coating on u-mo vs. al Interdiffusion
journal, April 2011

  • Ryu, Ho-Jin; Park, Jae-Soon; Park, Jong-Man
  • Nuclear Engineering and Technology, Vol. 43, Issue 2
  • DOI: 10.5516/NET.2011.43.2.159

In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al
journal, November 2014


Surface engineering of low enriched uranium–molybdenum
journal, September 2013


Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
journal, November 2013


Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2
journal, March 2015


Swift heavy ion irradiation induced interactions in the UMo/X/Al trilayer system (X=Ti, Zr, Nb, and Mo): RBS and μ-XRD studies
journal, March 2015


Diffusion Barrier Selection from Refractory Metals (Zr, Mo and Nb) Via Interdiffusion Investigation for U-Mo RERTR Fuel Alloy
journal, November 2013

  • Huang, K.; Kammerer, C. C.; Keiser, D. D.
  • Journal of Phase Equilibria and Diffusion, Vol. 35, Issue 2
  • DOI: 10.1007/s11669-013-0270-x

Interdiffusion and reaction between Zr and Al alloys from 425° to 625 °C
journal, June 2014


Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C
journal, November 2017


SRIM – The stopping and range of ions in matter (2010)
journal, June 2010

  • Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
  • DOI: 10.1016/j.nimb.2010.02.091

On the use of SRIM for computing radiation damage exposure
journal, September 2013

  • Stoller, R. E.; Toloczko, M. B.; Was, G. S.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310
  • DOI: 10.1016/j.nimb.2013.05.008

MODELING OF INTERACTION LAYER GROWTH BETWEEN U-Mo PARTICLES AND AN Al MATRIX
journal, December 2013

  • Kim, Yeon Soo; Hofman, G. L.; Ryu, Ho Jin
  • Nuclear Engineering and Technology, Vol. 45, Issue 7
  • DOI: 10.5516/NET.07.2013.713

Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe
journal, September 2015


Phase decomposition and bubble evolution in Xe implanted U3Si2 at 450∘C
journal, May 2019


Microstructure investigations of U3Si2 implanted by high-energy Xe ions at 600 °C
journal, May 2018


Nano-crystallization induced by high-energy heavy ion irradiation in UO2
journal, October 2018


Uranium–molybdenum nuclear fuel plates behaviour under heavy ion irradiation: An X-ray diffraction analysis
journal, March 2009


Heavy ion irradiation of U–Mo/Al dispersion fuel
journal, October 2006


Heavy ion irradiation of UMo/Al samples PVD coated with Si and ZrN layers
journal, March 2013


Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry
journal, April 2019


Interaction between Al and atomic layer deposited (ALD) ZrN under high-energy heavy ion irradiation
journal, February 2019


Investigation of High-Energy Ion-Irradiated MA957 Using Synchrotron Radiation under In-Situ Tension
journal, January 2016


High-energy synchrotron study of in-pile-irradiated U–Mo fuels
journal, March 2016


MeV per nucleon ion irradiation of nuclear materials with high energy synchrotron X-ray characterization
journal, April 2016