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

Abstract

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.

Authors:

^[1];

^[2];

^[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)

Publication Date:: Fri Feb 07 00:00:00 EST 2020

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

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

OSTI Identifier:: 1631115

Report Number(s):: INL/JOU-19-55305-Rev000
Journal ID: ISSN 0029-5639; TRN: US2200740

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

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Science and Engineering

Additional Journal Information:: Journal Volume: 194; Journal Issue: 6; Journal ID: ISSN 0029-5639

Publisher:: American Nuclear Society - Taylor & Francis

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; 37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; FCCI; fuel additive; U-10Zr metallic fuel; additive antimony; diffusion couple tests

Citation Formats


                    Zhuo, Weiqian, Xie, Yi, Benson, Michael T., Yang, Qiufeng, Mariani, Robert D., and Zhang, Jinsuo. Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding.  United States: N. p., 2020. 
Web.  doi:10.1080/00295639.2020.1713656.

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                    Zhuo, Weiqian, Xie, Yi, Benson, Michael T., Yang, Qiufeng, Mariani, Robert D., & Zhang, Jinsuo. Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding.  United States.  https://doi.org/10.1080/00295639.2020.1713656

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                    Zhuo, Weiqian, Xie, Yi, Benson, Michael T., Yang, Qiufeng, Mariani, Robert D., and Zhang, Jinsuo. Fri .  
"Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding".  United States.  https://doi.org/10.1080/00295639.2020.1713656.  https://www.osti.gov/servlets/purl/1631115.

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@article{osti_1631115,

  title        = {Experimental Investigation of FCCI Using Diffusion Couple Test Between UZr Fuel with Sb Additive and Cladding},

  author       = {Zhuo, Weiqian and Xie, Yi and Benson, Michael T. and Yang, Qiufeng and Mariani, Robert D. and Zhang, Jinsuo},

  abstractNote = {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.},

  doi          = {10.1080/00295639.2020.1713656},

  journal      = {Nuclear Science and Engineering},

  number       = 6,

  volume       = 194,

  place        = {United States},

  year         = {Fri Feb 07 00:00:00 EST 2020},

  month        = {Fri Feb 07 00:00:00 EST 2020}

}

Copy to clipboard

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

Abstract

Citation Formats

Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review journal, June 2017

Reactions between U–Zr alloys and Fe at 1003K journal, October 2013

Metallic fast reactor fuels journal, January 1997

Performance of a diffusion barrier under a fuel–clad chemical interaction (FCCI) journal, November 2009

Diffusion behaviors between metallic fuel alloys with Pd addition and Fe journal, November 2019

Diffusion behavior in an interface between U–10Zr alloy and HT-9 steel 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) journal, April 2014

Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel journal, January 2019

Reactions between U–Zr alloys and Fe at 923 K journal, December 1997

Modeling of In, Tl, Ga, Sb, and Pd as lanthanides binding agents in U-Zr metallic nuclear fuels journal, January 2012

Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys journal, April 1993

Formation of nitrides at the surface of U–Zr alloys journal, March 2001

Diffusion behavior of lanthanide-additive compounds (Ce4Sb3, Ce2Sb, and CeTe) against HT9 and Fe journal, April 2019

Metal Fuel-Cladding Interaction book, January 2012

Experimentally Known Properties of U-10Zr Alloys: A Critical Review journal, April 2018

Lanthanides in metallic nuclear fuels: Their behavior and methods for their control journal, December 2011

Interdiffusion between U-Zr fuelvs selected cladding steels journal, August 1994

Lanthanide migration and immobilization in metallic fuels journal, November 2018

Reactions of U–Zr alloy with Fe and Fe–Cr alloy journal, November 1999

Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review
journal, June 2017

Reactions between U–Zr alloys and Fe at 1003K
journal, October 2013

Metallic fast reactor fuels
journal, January 1997

Performance of a diffusion barrier under a fuel–clad chemical interaction (FCCI)
journal, November 2009

Diffusion behaviors between metallic fuel alloys with Pd addition and Fe
journal, November 2019

Diffusion behavior in an interface between U–10Zr alloy and HT-9 steel
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)
journal, April 2014

Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel
journal, January 2019

Reactions between U–Zr alloys and Fe at 923 K
journal, December 1997

Modeling of In, Tl, Ga, Sb, and Pd as lanthanides binding agents in U-Zr metallic nuclear fuels
journal, January 2012

Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys
journal, April 1993

Formation of nitrides at the surface of U–Zr alloys
journal, March 2001

Diffusion behavior of lanthanide-additive compounds (Ce4Sb3, Ce2Sb, and CeTe) against HT9 and Fe
journal, April 2019

Metal Fuel-Cladding Interaction
book, January 2012

Experimentally Known Properties of U-10Zr Alloys: A Critical Review
journal, April 2018

Lanthanides in metallic nuclear fuels: Their behavior and methods for their control
journal, December 2011

Interdiffusion between U-Zr fuelvs selected cladding steels
journal, August 1994

Lanthanide migration and immobilization in metallic fuels
journal, November 2018

Reactions of U–Zr alloy with Fe and Fe–Cr alloy
journal, November 1999