A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

Pizzocri, D.; Pastore, G.; Barani, T.; Magni, A.; Luzzi, L.; Van Uffelen, P.; Pitts, S. A.; Alfonsi, A.; Hales, J. D.

doi:10.1016/j.jnucmat.2018.02.024

Title: A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

Abstract

The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear fuel. In this work, we present a model representing the evolution of intra-granular bubbles in terms of bubble number density and average bubble size. The model considers the fundamental processes of single gas atom diffusion, gas bubble nucleation, bubble re-solution, and gas atom trapping at bubbles. The model is derived from a detailed cluster dynamics formulation yet consists of only three differential equations in its final form; hence, it can be efficiently applied in engineering fuel performance codes while retaining a physical basis. We discuss the improvements made in our model in comparison to previous models for intra-granular bubble evolution. We validate the model against experimental data, both in terms of bubble number density and average bubble radius. Lastly, we perform an uncertainty analysis, by propagating the uncertainties in the parameters to the model results.

Authors:

; Pastore, G.;

; Magni, A.;

; Van Uffelen, P.;

; Alfonsi, A.;

Publication Date:: Sun Apr 01 00:00:00 EDT 2018

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

Sponsoring Org.:: USDOE Office of Energy Efficiency and Renewable Energy (EERE)

OSTI Identifier:: 1421777

Alternate Identifier(s):: OSTI ID: 1631707

Report Number(s):: INL/JOU-17-43663-Rev000
Journal ID: ISSN 0022-3115; S0022311517315039; PII: S0022311517315039

Grant/Contract Number:: SC0016464; 754329; AC07-05ID14517

Resource Type:: Published Article

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Name: Journal of Nuclear Materials Journal Volume: 502 Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Fission gas

Citation Formats


                    Pizzocri, D., Pastore, G., Barani, T., Magni, A., Luzzi, L., Van Uffelen, P., Pitts, S. A., Alfonsi, A., and Hales, J. D. A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools.  Netherlands: N. p., 2018. 
Web.  doi:10.1016/j.jnucmat.2018.02.024.

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                    Pizzocri, D., Pastore, G., Barani, T., Magni, A., Luzzi, L., Van Uffelen, P., Pitts, S. A., Alfonsi, A., & Hales, J. D. A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools.  Netherlands.  https://doi.org/10.1016/j.jnucmat.2018.02.024

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                    Pizzocri, D., Pastore, G., Barani, T., Magni, A., Luzzi, L., Van Uffelen, P., Pitts, S. A., Alfonsi, A., and Hales, J. D. Sun .  
"A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools".  Netherlands.  https://doi.org/10.1016/j.jnucmat.2018.02.024.

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@article{osti_1421777,

  title        = {A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools},

  author       = {Pizzocri, D. and Pastore, G. and Barani, T. and Magni, A. and Luzzi, L. and Van Uffelen, P. and Pitts, S. A. and Alfonsi, A. and Hales, J. D.},

  abstractNote = {The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear fuel. In this work, we present a model representing the evolution of intra-granular bubbles in terms of bubble number density and average bubble size. The model considers the fundamental processes of single gas atom diffusion, gas bubble nucleation, bubble re-solution, and gas atom trapping at bubbles. The model is derived from a detailed cluster dynamics formulation yet consists of only three differential equations in its final form; hence, it can be efficiently applied in engineering fuel performance codes while retaining a physical basis. We discuss the improvements made in our model in comparison to previous models for intra-granular bubble evolution. We validate the model against experimental data, both in terms of bubble number density and average bubble radius. Lastly, we perform an uncertainty analysis, by propagating the uncertainties in the parameters to the model results.},

  doi          = {10.1016/j.jnucmat.2018.02.024},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 502,

  place        = {Netherlands},

  year         = {Sun Apr 01 00:00:00 EDT 2018},

  month        = {Sun Apr 01 00:00:00 EDT 2018}

}

Copy to clipboard

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Similar Records

Title: A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

Abstract

Citation Formats

Development of a multiscale thermal conductivity model for fission gas in UO2 journal, February 2016

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up journal, November 2005

Nucleation and growth of intragranular defect and insoluble atom clusters in nuclear oxide fuels journal, April 2012

The nucleation and growth of gas bubbles in irradiated metals journal, June 1990

Master equation and Fokker–Planck methods for void nucleation and growth in irradiation swelling journal, February 2004

Intragranular Xe bubble population evolution in UO2: A first passage Monte Carlo simulation approach journal, July 2010

Molecular dynamics study of Xe bubble re-solution in UO2 journal, January 2012

Molecular dynamic simulation of fission fragment induced thermal spikes in UO2: Sputtering and bubble re-solution journal, April 2010

The effect of fission spikes on fission gas re-solution journal, January 1973

Modelling of fission gas release and gaseous swelling of light water reactor fuels journal, April 1997

MARGARET: A comprehensive code for the description of fission gas behavior journal, June 2011

The distribution of intragranular fission gas bubbles in UO2 during irradiation journal, February 1971

Re-solution of fission gas – A review: Part I. Intragranular bubbles journal, August 2006

The development of grain-face porosity in irradiated oxide fuel journal, February 2004

The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pins journal, May 1977

Molecular dynamics simulation of intragranular Xe bubble re-solution in UO2 journal, July 2009

The mobility of intragranular bubbles in uranium dioxide during irradiation journal, November 1976

On the theory of fission gas bubble evolution in irradiated UO2 fuel journal, January 2000

Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS journal, April 2017

A NRA study of temperature and heavy ion irradiation effects on helium migration in sintered uranium dioxide journal, October 2006

High resolution TEM of high burnup UO2 fuel journal, December 1997

Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis journal, March 2013

Modelling of grain face bubbles coalescence in irradiated UO2 fuel journal, February 2008

Gas release mechanisms in UO 2 —a critical review journal, January 1980

A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation journal, August 1969

Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling journal, January 2015

The stability of gas bubbles in an irradiation environment journal, June 1969

A new fission-gas release model journal, August 1983

On the behaviour of intragranular fission gas in UO2 fuel journal, June 2000

Theory of Helium Dissolution in Uranium Dioxide. II. Helium Solubility journal, August 1965

Theory of diffusion-limited precipitation journal, September 1958

The principles of nucleation theory relevant to the void swelling problem journal, March 1980

Multiscale Modelling for the Fission gas Behaviour in the Transuranus code journal, December 2011

Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6–83 GWd/t journal, November 1993

PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release journal, September 2016

Development of a multiscale thermal conductivity model for fission gas in UO2
journal, February 2016

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up
journal, November 2005

Nucleation and growth of intragranular defect and insoluble atom clusters in nuclear oxide fuels
journal, April 2012

The nucleation and growth of gas bubbles in irradiated metals
journal, June 1990

Master equation and Fokker–Planck methods for void nucleation and growth in irradiation swelling
journal, February 2004

Intragranular Xe bubble population evolution in UO2: A first passage Monte Carlo simulation approach
journal, July 2010

Molecular dynamics study of Xe bubble re-solution in UO2
journal, January 2012

Molecular dynamic simulation of fission fragment induced thermal spikes in UO2: Sputtering and bubble re-solution
journal, April 2010

The effect of fission spikes on fission gas re-solution
journal, January 1973

Modelling of fission gas release and gaseous swelling of light water reactor fuels
journal, April 1997

MARGARET: A comprehensive code for the description of fission gas behavior
journal, June 2011

The distribution of intragranular fission gas bubbles in UO2 during irradiation
journal, February 1971

Re-solution of fission gas – A review: Part I. Intragranular bubbles
journal, August 2006

The development of grain-face porosity in irradiated oxide fuel
journal, February 2004

The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pins
journal, May 1977

Molecular dynamics simulation of intragranular Xe bubble re-solution in UO2
journal, July 2009

The mobility of intragranular bubbles in uranium dioxide during irradiation
journal, November 1976

On the theory of fission gas bubble evolution in irradiated UO2 fuel
journal, January 2000

Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS
journal, April 2017

A NRA study of temperature and heavy ion irradiation effects on helium migration in sintered uranium dioxide
journal, October 2006

High resolution TEM of high burnup UO2 fuel
journal, December 1997

Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis
journal, March 2013

Modelling of grain face bubbles coalescence in irradiated UO2 fuel
journal, February 2008

Gas release mechanisms in UO ₂ —a critical review
journal, January 1980

A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation
journal, August 1969

Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling
journal, January 2015

The stability of gas bubbles in an irradiation environment
journal, June 1969

A new fission-gas release model
journal, August 1983

On the behaviour of intragranular fission gas in UO2 fuel
journal, June 2000

Theory of Helium Dissolution in Uranium Dioxide. II. Helium Solubility
journal, August 1965

Theory of diffusion-limited precipitation
journal, September 1958

The principles of nucleation theory relevant to the void swelling problem
journal, March 1980

Multiscale Modelling for the Fission gas Behaviour in the Transuranus code
journal, December 2011

Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6–83 GWd/t
journal, November 1993

PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release
journal, September 2016