A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient

Wang, Yafeng; Xiao, Zhihua; Hu, Shenyang; Li, Yulan; Shi, San-Qiang

doi:10.1016/j.commatsci.2020.109817

Title: A phase field study of the thermal migration of gas bubbles in UO₂ nuclear fuel under temperature gradient

Abstract

Phase field models are developed to study the gas bubble migration in uranium dioxide nuclear fuel in which a large temperature gradient exists during the operation. In this work, thermal diffusion mechanism for nanosized gas bubbles and vapor transport process for micron-sized gas bubbles are considered, respectively. In both cases, gas bubbles migrate to the high-temperature area. Due to the velocity difference between leading and trailing edges of the gas bubbles, nanosized gas bubbles are elongated along the temperature gradient direction when thermal diffusion is dominated. Micron-sized gas bubbles are either compressed along temperature gradient direction to form lenticular shape bubbles or elongated along temperature gradient direction, depending on the location of the gas bubbles within the fuel pellet. Initial gas bubble radius has no significant effect on the gas bubble migration velocity for both thermal diffusion and vapor transport mechanisms. We notice that the shape change of the gas bubble due to vapor transport mechanism has no significant effect on the migration velocity. Furthermore, the center cavity formation is also captured by our model which is due to the migration and accumulation of lenticular gas bubbles at the center of the fuel pellet. The modeling results compare well withmore »« less

Authors:

^[1]; Xiao, Zhihua ^[1];

^[2]; Li, Yulan ^[2]; Shi, San-Qiang ^[1]

Hong Kong Polytechnic Univ., Shenzhen (China). Shenzhen Research Inst.; Hong Kong Polytechnic Univ., Kowloon (Hong Kong)
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

Publication Date:: Fri May 29 00:00:00 EDT 2020

Research Org.:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE; National Natural Science Foundation of China (NSFC); Research Grants Council of Hong Kong

OSTI Identifier:: 1639154

Report Number(s):: PNNL-SA-153026
Journal ID: ISSN 0927-0256; TRN: US2201848

Grant/Contract Number:: AC05-76RL01830; 51672232; 152636/16E

Resource Type:: Accepted Manuscript

Journal Name:: Computational Materials Science

Additional Journal Information:: Journal Volume: 183; Journal ID: ISSN 0927-0256

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; gas bubble migration, quantitative phase-field modeling, temperature gradient

Citation Formats


                    Wang, Yafeng, Xiao, Zhihua, Hu, Shenyang, Li, Yulan, and Shi, San-Qiang. A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient.  United States: N. p., 2020. 
Web.  doi:10.1016/j.commatsci.2020.109817.

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                    Wang, Yafeng, Xiao, Zhihua, Hu, Shenyang, Li, Yulan, & Shi, San-Qiang. A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient.  United States.  https://doi.org/10.1016/j.commatsci.2020.109817

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                    Wang, Yafeng, Xiao, Zhihua, Hu, Shenyang, Li, Yulan, and Shi, San-Qiang. Fri .  
"A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient".  United States.  https://doi.org/10.1016/j.commatsci.2020.109817.  https://www.osti.gov/servlets/purl/1639154.

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@article{osti_1639154,

  title        = {A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient},

  author       = {Wang, Yafeng and Xiao, Zhihua and Hu, Shenyang and Li, Yulan and Shi, San-Qiang},

  abstractNote = {Phase field models are developed to study the gas bubble migration in uranium dioxide nuclear fuel in which a large temperature gradient exists during the operation. In this work, thermal diffusion mechanism for nanosized gas bubbles and vapor transport process for micron-sized gas bubbles are considered, respectively. In both cases, gas bubbles migrate to the high-temperature area. Due to the velocity difference between leading and trailing edges of the gas bubbles, nanosized gas bubbles are elongated along the temperature gradient direction when thermal diffusion is dominated. Micron-sized gas bubbles are either compressed along temperature gradient direction to form lenticular shape bubbles or elongated along temperature gradient direction, depending on the location of the gas bubbles within the fuel pellet. Initial gas bubble radius has no significant effect on the gas bubble migration velocity for both thermal diffusion and vapor transport mechanisms. We notice that the shape change of the gas bubble due to vapor transport mechanism has no significant effect on the migration velocity. Furthermore, the center cavity formation is also captured by our model which is due to the migration and accumulation of lenticular gas bubbles at the center of the fuel pellet. The modeling results compare well with experimental observations and theoretical analysis in the literature.},

  doi          = {10.1016/j.commatsci.2020.109817},

  journal      = {Computational Materials Science},

  number       = ,

  volume       = 183,

  place        = {United States},

  year         = {Fri May 29 00:00:00 EDT 2020},

  month        = {Fri May 29 00:00:00 EDT 2020}

}

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Title: A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient

Abstract

Citation Formats

Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases journal, June 1998

Experimental evidence of Xe incorporation in Schottky defects in UO 2 journal, March 2015

Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO2 journal, November 2015

Free energy of Xe incorporation at point defects and in nanovoids and bubbles in UO 2 journal, April 2012

Trapping and solution of fission Xe in UO2. journal, January 1985

In situ TEM study of temperature-induced fission product precipitation in UO2 journal, June 2008

Fission gas bubbles and recrystallization-induced degradation of the effective thermal conductivity in U-7Mo fuels journal, December 2018

Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation journal, August 2011

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM journal, March 2006

Thermophysical properties of uranium dioxide journal, March 2000

Bubble migration in UO2—A study using a laser image furnace journal, December 1970

Grain Growth in Sintered Uranium Dioxide: II, Columnar Grain Growth journal, January 1962

On the thermal gradient migration of lenticular voids journal, October 1979

Xenon migration in UO2 under irradiation studied by SIMS profilometry journal, September 2013

Xenon migration in UO2: A SIMS study journal, May 2012

Migration rate of lenticular voids in UO2 under the influence of temperature gradient journal, September 1977

The Soret Effect: A Review of Recent Experimental Results journal, April 2005

The migration of gas bubbles in material subject to a temperature gradient journal, January 1964

The kinetics of pore movement in UO2 fuel rods journal, June 1972

Simulation of Grain Growth and Pore Migration in a Thermal Gradient journal, March 1998

Atomistic simulations of void migration under thermal gradient in UO2 journal, January 2010

Phase-field modeling of temperature gradient driven pore migration coupling with thermal conduction journal, April 2012

Phase-field simulations of pore migration and morphology change in thermal gradients journal, July 2017

Phase-field simulation of void migration in a temperature gradient journal, May 2010

Phase-field modeling of void migration and growth kinetics in materials under irradiation and temperature field journal, December 2010

Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method journal, September 2018

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials journal, April 2017

Phase-field modeling of fission gas bubble growth on grain boundaries and triple junctions in UO2 nuclear fuel journal, April 2019

How to apply the phase field method to model radiation damage journal, May 2018

Fundamental aspects of nuclear reactor fuel elements report, January 1976

On the diffusional mobilities of particles, pores and loops journal, February 1972

Kinetics of diffusional motion of pores in solids journal, April 1969

Phase-field model for binary alloys journal, December 1999

Surface energy measurements on UO2 — A critical review journal, May 1987

High resolution TEM observation and density estimation of Xe bubbles in high burnup UO2 fuels journal, May 1998

Free Energy of a Nonuniform System. I. Interfacial Free Energy journal, February 1958

A quantitative phase field model for hydride precipitation in zirconium alloys: Part II. Modeling of temperature dependent hydride precipitation journal, April 2015

On spinodal decomposition journal, September 1961

Phase-field simulation of irradiated metals journal, January 2011

Effect of damage rate on the kinetics of void nucleation and growth by phase field modeling for materials under irradiations journal, November 2016

Theory of columnar grain growth and central void formation in oxide fuel rods journal, May 1967

Atomic diffusion mechanism of Xe in UO2 journal, August 2008

Atomic transport properties in UO2 and mixed oxides (U, Pu)O2 journal, January 1987

The migration of intragranular fission gas bubbles in irradiated uranium dioxide journal, December 1977

Title: A phase field study of the thermal migration of gas bubbles in UO₂ nuclear fuel under temperature gradient

Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases
journal, June 1998

Experimental evidence of Xe incorporation in Schottky defects in UO ₂
journal, March 2015

Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO2
journal, November 2015

Free energy of Xe incorporation at point defects and in nanovoids and bubbles in ${UO}_{2}$
journal, April 2012

Trapping and solution of fission Xe in UO2.
journal, January 1985

In situ TEM study of temperature-induced fission product precipitation in UO2
journal, June 2008

Fission gas bubbles and recrystallization-induced degradation of the effective thermal conductivity in U-7Mo fuels
journal, December 2018

Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation
journal, August 2011

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM
journal, March 2006

Thermophysical properties of uranium dioxide
journal, March 2000

Bubble migration in UO2—A study using a laser image furnace
journal, December 1970

Grain Growth in Sintered Uranium Dioxide: II, Columnar Grain Growth
journal, January 1962

On the thermal gradient migration of lenticular voids
journal, October 1979

Xenon migration in UO2 under irradiation studied by SIMS profilometry
journal, September 2013

Xenon migration in UO2: A SIMS study
journal, May 2012

Migration rate of lenticular voids in UO2 under the influence of temperature gradient
journal, September 1977

The Soret Effect: A Review of Recent Experimental Results
journal, April 2005

The migration of gas bubbles in material subject to a temperature gradient
journal, January 1964

The kinetics of pore movement in UO2 fuel rods
journal, June 1972

Simulation of Grain Growth and Pore Migration in a Thermal Gradient
journal, March 1998

Atomistic simulations of void migration under thermal gradient in UO2
journal, January 2010

Phase-field modeling of temperature gradient driven pore migration coupling with thermal conduction
journal, April 2012

Phase-field simulations of pore migration and morphology change in thermal gradients
journal, July 2017

Phase-field simulation of void migration in a temperature gradient
journal, May 2010

Phase-field modeling of void migration and growth kinetics in materials under irradiation and temperature field
journal, December 2010

Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method
journal, September 2018

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials
journal, April 2017

Phase-field modeling of fission gas bubble growth on grain boundaries and triple junctions in UO2 nuclear fuel
journal, April 2019

How to apply the phase field method to model radiation damage
journal, May 2018

Fundamental aspects of nuclear reactor fuel elements
report, January 1976

On the diffusional mobilities of particles, pores and loops
journal, February 1972

Kinetics of diffusional motion of pores in solids
journal, April 1969

Phase-field model for binary alloys
journal, December 1999

Surface energy measurements on UO2 — A critical review
journal, May 1987

High resolution TEM observation and density estimation of Xe bubbles in high burnup UO2 fuels
journal, May 1998

Free Energy of a Nonuniform System. I. Interfacial Free Energy
journal, February 1958

A quantitative phase field model for hydride precipitation in zirconium alloys: Part II. Modeling of temperature dependent hydride precipitation
journal, April 2015

On spinodal decomposition
journal, September 1961

Phase-field simulation of irradiated metals
journal, January 2011

Effect of damage rate on the kinetics of void nucleation and growth by phase field modeling for materials under irradiations
journal, November 2016

Theory of columnar grain growth and central void formation in oxide fuel rods
journal, May 1967

Atomic diffusion mechanism of Xe in UO2
journal, August 2008

Atomic transport properties in UO2 and mixed oxides (U, Pu)O2
journal, January 1987

The migration of intragranular fission gas bubbles in irradiated uranium dioxide
journal, December 1977