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:
-
- Korea Atomic Energy Research Inst., Daejeon (South Korea)
- 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. doi: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}
}
Web of Science
Works referenced in this record:
Irradiation behavior of low-enriched U6Fe-Ai dispersion fuel elements
journal, October 1987
- Hofman, G. L.; Domagala, R. F.; Copeland, G. L.
- Journal of Nuclear Materials, Vol. 150, Issue 2
Irradiation behavior of U6Mn–Al dispersion fuel elements
journal, April 2000
- Meyer, M. K.; Wiencek, T. C.; Hayes, S. L.
- Journal of Nuclear Materials, Vol. 278, Issue 2-3
Development of very-high-density low-enriched-uranium fuels
journal, December 1997
- Snelgrove, J. L.; Hofman, G. L.; Meyer, M. K.
- Nuclear Engineering and Design, Vol. 178, Issue 1
Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002
- Meyer, M. K.; Hofman, G. L.; Hayes, S. L.
- Journal of Nuclear Materials, Vol. 304, Issue 2-3
Radiation-Induced Recrystallization of U-Mo Fuel Particles and Radiation-Induced Amorphization of Interaction Products in U-Mo/Al Dispersion Fuel
journal, October 2007
- Ryu, Ho Jin; Kim, Yeon Soo; Hofman, G. L.
- Materials Science Forum, Vol. 558-559
Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel
journal, April 2008
- Van den Berghe, S.; Van Renterghem, W.; Leenaers, A.
- Journal of Nuclear Materials, Vol. 375, Issue 3
Effect of Si and Zr on the interdiffusion of U–Mo alloy and Al
journal, March 2008
- Park, Jong Man; Ryu, Ho Jin; Oh, Seok Jin
- Journal of Nuclear Materials, Vol. 374, Issue 3
Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix
journal, May 2011
- Leenaers, A.; Van den Berghe, S.; Van Renterghem, W.
- Journal of Nuclear Materials, Vol. 412, Issue 1
AlSi matrices for U(Mo) dispersion fuel plates
journal, August 2013
- Leenaers, A.; Van den Berghe, S.; Detavernier, C.
- Journal of Nuclear Materials, Vol. 439, Issue 1-3
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
In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al
journal, November 2014
- Kim, Yeon Soo; Park, J. M.; Lee, K. H.
- Journal of Nuclear Materials, Vol. 454, Issue 1-3
Surface engineering of low enriched uranium–molybdenum
journal, September 2013
- Leenaers, A.; Van den Berghe, S.; Detavernier, C.
- Journal of Nuclear Materials, Vol. 440, Issue 1-3
Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
journal, November 2013
- Van den Berghe, S.; Parthoens, Y.; Cornelis, G.
- Journal of Nuclear Materials, Vol. 442, Issue 1-3
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
- Leenaers, A.; Van den Berghe, S.; Koonen, E.
- Journal of Nuclear Materials, Vol. 458
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
- Chiang, H. -Y.; Park, S. -H.; Mayer, M.
- Journal of Alloys and Compounds, Vol. 626
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
Interdiffusion and reaction between Zr and Al alloys from 425° to 625 °C
journal, June 2014
- Dickson, J.; Zhou, L.; Paz y. Puente, A.
- Intermetallics, Vol. 49
Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy
journal, September 2012
- Huang, K.; Park, Y.; Keiser, D. D.
- Journal of Phase Equilibria and Diffusion, Vol. 33, Issue 6
Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C
journal, November 2017
- Miao, Yinbin; Harp, Jason; Mo, Kun
- Journal of Nuclear Materials, Vol. 495
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
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
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
Electron Microscopy of Barrier Coatings on Uranium-Molybdenum Fuel Irradiated to Burnup 60%
journal, February 2017
- Golosov, O. A.; Averin, S. A.; Lyutikova, M. S.
- Atomic Energy, Vol. 121, Issue 4
Dependence of thickness, morphology, and crystallographic properties of Mo and ZrN coatings on U-Mo substrate size
journal, December 2018
- Kim, Ji-Hyeon; Jeong, Gwan Yoon; Kim, Sunghwan
- Journal of Nuclear Materials, Vol. 512
Reaction layer growth and reaction heat of U–Mo/Al dispersion fuels using centrifugally atomized powders
journal, September 2003
- Ryu, Ho Jin; Han, Young Soo; Park, Jong Man
- Journal of Nuclear Materials, Vol. 321, Issue 2-3
U-W (Uranium-Tungsten)
journal, May 2009
- Okamoto, H.
- Journal of Phase Equilibria and Diffusion, Vol. 30, Issue 4
Al-Zr (Aluminum-Zirconium)
journal, October 2002
- Okamoto, H.
- Journal of Phase Equilibria, Vol. 23, Issue 5
Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe
journal, September 2015
- Ye, B.; Bhattacharya, S.; Mo, K.
- Journal of Nuclear Materials, Vol. 464
Phase decomposition and bubble evolution in Xe implanted U3Si2 at 450∘C
journal, May 2019
- Miao, Yinbin; Harp, Jason; Mo, Kun
- Journal of Nuclear Materials, Vol. 518
Microstructure investigations of U3Si2 implanted by high-energy Xe ions at 600 °C
journal, May 2018
- Miao, Yinbin; Harp, Jason; Mo, Kun
- Journal of Nuclear Materials, Vol. 503
Nano-crystallization induced by high-energy heavy ion irradiation in UO2
journal, October 2018
- Miao, Yinbin; Yao, Tiankai; Lian, Jie
- Scripta Materialia, Vol. 155
Uranium–molybdenum nuclear fuel plates behaviour under heavy ion irradiation: An X-ray diffraction analysis
journal, March 2009
- Palancher, H.; Wieschalla, N.; Martin, P.
- Journal of Nuclear Materials, Vol. 385, Issue 2
Heavy ion irradiation of U–Mo/Al dispersion fuel
journal, October 2006
- Wieschalla, N.; Bergmaier, A.; Böni, P.
- Journal of Nuclear Materials, Vol. 357, Issue 1-3
Heavy ion irradiation of UMo/Al samples PVD coated with Si and ZrN layers
journal, March 2013
- Jungwirth, R.; Zweifel, T.; Chiang, H. -Y.
- Journal of Nuclear Materials, Vol. 434, Issue 1-3
Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry
journal, April 2019
- Gong, Bowen; Frazer, David; Yao, Tiankai
- Journal of Nuclear Materials, Vol. 516
Interaction between Al and atomic layer deposited (ALD) ZrN under high-energy heavy ion irradiation
journal, February 2019
- Bhattacharya, Sumit; Liu, Xiang; Miao, Yinbin
- Acta Materialia, Vol. 164
Characterization of high energy Xe ion irradiation effects in single crystal molybdenum with depth-resolved synchrotron microbeam diffraction
journal, April 2016
- Yun, Di; Miao, Yinbin; Xu, Ruqing
- Journal of Nuclear Materials, Vol. 471
Investigation of High-Energy Ion-Irradiated MA957 Using Synchrotron Radiation under In-Situ Tension
journal, January 2016
- Mo, Kun; Yun, Di; Miao, Yinbin
- Materials, Vol. 9, Issue 1
High-energy synchrotron study of in-pile-irradiated U–Mo fuels
journal, March 2016
- Miao, Yinbin; Mo, Kun; Ye, Bei
- Scripta Materialia, Vol. 114
MeV per nucleon ion irradiation of nuclear materials with high energy synchrotron X-ray characterization
journal, April 2016
- Pellin, M. J.; Yacout, Abdellatif M.; Mo, Kun
- Journal of Nuclear Materials, Vol. 471