Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding

Zhuo, Weiqian; Xie, Yi; Benson, Michael T.; Yang, Qiufeng; Mariani, Robert D.; Zhang, Jinsuo

doi:10.1080/00295639.2020.1713656

Title: Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding

Journal Article · Fri Feb 07 00:00:00 EST 2020 · Nuclear Science and Engineering

DOI:https://doi.org/10.1080/00295639.2020.1713656· OSTI ID:1631115

^[1];

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^[2]; Yang, Qiufeng ^[1];

^[2]; Zhang, Jinsuo ^[1]

Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Alloying additions are introduced into U-Zr fuel in order to bind lanthanides (e.g., cerium) and prevent their migration to the fuel-cladding interface. Antimony (Sb) is being investigated as a candidate additive. The present study focuses on the diffusion couple behavior of U-10Zr (wt%) alloy with Sb against cladding (iron or HT9) at 640°C. The diffusion cross sections were analyzed using a scanning electron microscope and X-ray diffraction. Zr-rind was found at the interface of the fuel alloy, Sb was found to be bound in Sb-Zr precipitates or Sb-Ce precipitates, and no reaction was found between Sb precipitates and the cladding materials.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC07-05ID14517; NE0008574

OSTI ID:: 1631115

Report Number(s):: INL/JOU-19-55305-Rev000; TRN: US2200740

Journal Information:: Nuclear Science and Engineering, Vol. 194, Issue 6; ISSN 0029-5639

Publisher:: American Nuclear Society - Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 4 works

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References (19)

Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review Matthews, Christopher; Unal, Cetin; Galloway, Jack Nuclear Technology, Vol. 198, Issue 3 https://doi.org/10.1080/00295450.2017.1323535	journal	June 2017
Reactions between U–Zr alloys and Fe at 1003K Ogata, Takanari; Nakamura, Kinya; Itoh, Akinori Journal of Nuclear Materials, Vol. 441, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.09.038	journal	October 2013
Metallic fast reactor fuels Hofman, G. L.; Walters, L. C.; Bauer, T. H. Progress in Nuclear Energy, Vol. 31, Issue 1-2 https://doi.org/10.1016/0149-1970(96)00005-4	journal	January 1997
Performance of a diffusion barrier under a fuel–clad chemical interaction (FCCI) Kim, Jun Hwan; Ryu, Ho Jin; Baek, Jong Hyuk Journal of Nuclear Materials, Vol. 394, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2009.08.018	journal	November 2009
Diffusion behaviors between metallic fuel alloys with Pd addition and Fe Xie, Yi; Benson, Michael T.; He, Lingfeng Journal of Nuclear Materials, Vol. 525 https://doi.org/10.1016/j.jnucmat.2019.07.028	journal	November 2019
Diffusion behavior in an interface between U–10Zr alloy and HT-9 steel Lee, Chong Tak; Kim, Hun; Kim, Tae Kyu Journal of Nuclear Materials, Vol. 395, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2009.10.044	journal	December 2009
Diffusional Interaction Between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C) Park, Y.; Huang, K.; Paz y. Puente, A. Metallurgical and Materials Transactions A, Vol. 46, Issue 1 https://doi.org/10.1007/s11661-014-2277-2	journal	April 2014
Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel Kaity, Santu; Banerjee, Joydipta; Parida, S. C. Journal of Nuclear Materials, Vol. 513 https://doi.org/10.1016/j.jnucmat.2018.10.041	journal	January 2019
Reactions between U–Zr alloys and Fe at 923 K Ogata, Takanari; Kurata, Masaki; Nakamura, Kinya Journal of Nuclear Materials, Vol. 250, Issue 2-3 https://doi.org/10.1016/S0022-3115(97)00262-6	journal	December 1997
Modeling of In, Tl, Ga, Sb, and Pd as lanthanides binding agents in U-Zr metallic nuclear fuels Bozzolo, Guillermo; Yacout, Abdellatif M.; Hofman, Gerard L. MRS Proceedings, Vol. 1444 https://doi.org/10.1557/opl.2012.915	journal	January 2012
Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys Keiser, D. D.; Dayananda, M. A. Journal of Nuclear Materials, Vol. 200, Issue 2 https://doi.org/10.1016/0022-3115(93)90334-U	journal	April 1993
Formation of nitrides at the surface of U–Zr alloys Akabori, M.; Itoh, A.; Ogawa, T. Journal of Nuclear Materials, Vol. 289, Issue 3 https://doi.org/10.1016/S0022-3115(01)00426-3	journal	March 2001
Diffusion behavior of lanthanide-additive compounds (Ce4Sb3, Ce2Sb, and CeTe) against HT9 and Fe Xie, Yi; Zhang, Jinsuo; Benson, Michael T. Materials Characterization, Vol. 150 https://doi.org/10.1016/j.matchar.2019.02.012	journal	April 2019
Metal Fuel-Cladding Interaction Keiser, Jr., D. D. Comprehensive Nuclear Materials https://doi.org/10.1016/B978-0-08-056033-5.00067-7	book	January 2012
Experimentally Known Properties of U-10Zr Alloys: A Critical Review Janney, Dawn E.; Hayes, Steven L. Nuclear Technology, Vol. 203, Issue 2 https://doi.org/10.1080/00295450.2018.1435137	journal	April 2018
Lanthanides in metallic nuclear fuels: Their behavior and methods for their control Mariani, R. D.; Porter, D. L.; O’Holleran, T. P. Journal of Nuclear Materials, Vol. 419, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.08.036	journal	December 2011
Interdiffusion between U-Zr fuelvs selected cladding steels Keiser, D. D.; Dayananda, M. A. Metallurgical and Materials Transactions A, Vol. 25, Issue 8 https://doi.org/10.1007/BF02668530	journal	August 1994
Lanthanide migration and immobilization in metallic fuels Xie, Yi; Zhang, Jinsuo; Li, Xiang Progress in Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.pnucene.2018.08.019	journal	November 2018
Reactions of U–Zr alloy with Fe and Fe–Cr alloy Nakamura, Kinya; Ogata, Takanari; Kurata, Masaki Journal of Nuclear Materials, Vol. 275, Issue 3 https://doi.org/10.1016/S0022-3115(99)00227-5	journal	November 1999

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Title: Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding

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