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Title: Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE
OSTI ID:
1631490
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 538 Journal Issue: C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 15 works
Citation information provided by
Web of Science

References (80)

Pipe diffusion at dislocations in UO2 journal April 2014
Multidimensional multiphysics simulation of nuclear fuel behavior journal April 2012
Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up journal November 2005
Bubble diffusion to grain boundaries in UO2 and metals during annealing: a new approach journal June 1994
Free energy of Xe incorporation at point defects and in nanovoids and bubbles in UO 2 journal April 2012
A method to calculate equilibrium concentrations of gas and defects in the vicinity of an over-pressured bubble in UO2 journal April 2014
Xe diffusion and bubble nucleation around edge dislocations in UO2 journal November 2015
Experimental evidence of Xe incorporation in Schottky defects in UO 2 journal March 2015
Molecular dynamics study of Xe bubble re-solution in UO2 journal January 2012
Vacancy Potential and Void Growth on Grain Boundaries journal January 1975
Model for evolution of crystal defects in UO2 under irradiation up to high burn-ups journal January 2009
Modelling of irradiated UO2 fuel behaviour under transient conditions journal June 2013
The effect of fission spikes on fission gas re-solution journal January 1973
Equation of State for Nonattracting Rigid Spheres journal July 1969
Modelling of fission gas release and gaseous swelling of light water reactor fuels journal April 1997
Modelling intragranular fission gas release in irradiation of sintered LWR UO2 fuel journal July 2002
MARGARET: A comprehensive code for the description of fission gas behavior journal June 2011
Influence of dislocation and dislocation loop biases on microstructures simulated by rate equation cluster dynamics journal December 2015
Development of the Enigma fuel Performance code for Whole core Analysis and dry Storage Assessments journal December 2011
A new equation of state for helium nanobubbles embedded in UO2 matrix calculated via molecular dynamics simulations journal May 2019
Radiation-induced microstructural change in high burnup UO2 fuel pellets journal June 1994
High resolution TEM observation and density estimation of Xe bubbles in high burnup UO2 fuels journal May 1998
Re-solution of fission gas – A review: Part I. Intragranular bubbles journal August 2006
Molecular dynamics simulation of intragranular Xe bubble re-solution in UO2 journal July 2009
The effect of internal pressure on the coarsening of inert gas bubbles in metals journal October 1989
Multiscale simulation of xenon diffusion and grain boundary segregation in UO2 journal July 2015
An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel journal May 2008
Irradiation-induced heterogeneous nucleation in uranium dioxide journal July 2010
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis journal March 2013
Atomistic model of xenon gas bubble re-solution rate due to thermal spike in uranium oxide journal August 2018
Interaction of stresses with inclusions in solids — a review journal September 1980
Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel journal January 2006
The stability of gas bubbles in an irradiation environment journal June 1969
Bubble evolution in Kr-irradiated UO2 during annealing journal December 2017
A new fission-gas release model journal August 1983
The kinetics of precipitation from supersaturated solid solutions journal April 1961
Physical processes and mechanisms related to fission gas swelling in MX-type nuclear fuels journal October 1979
Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory journal August 1978
Multiscale Modelling for the Fission gas Behaviour in the Transuranus code journal December 2011
Fission gas release from UO2 nuclear fuel: A review journal January 2019
Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6–83 GWd/t journal November 1993
TRANSURANUS: a fuel rod analysis code ready for use journal June 1992
Nucleation and growth of intragranular defect and insoluble atom clusters in nuclear oxide fuels journal April 2012
An improved equation of state for inert gases at high pressures journal December 1980
Intragranular Xe bubble population evolution in UO2: A first passage Monte Carlo simulation approach journal July 2010
The migration of intragranular fission gas bubbles in irradiated uranium dioxide journal December 1977
An electron microscope examination of matrix fission-gas bubbles in irradiated uranium dioxide journal March 1971
Review Progress in Ostwald ripening theories and their applications to nickel-base superalloys Part I: Ostwald ripening theories journal January 2002
The distribution of intragranular fission gas bubbles in UO2 during irradiation journal February 1971
On the coarsening mechanisms of helium bubbles — Ostwald ripening versus migration and coalescence journal March 1991
The development of grain-face porosity in irradiated oxide fuel journal February 2004
Modelling of fission gas release from irradiated UO2 fuel under high-temperature annealing conditions journal November 2012
XAS characterisation of xenon bubbles in uranium dioxide journal June 2008
The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pins journal May 1977
Segregation of xenon to dislocations and grain boundaries in uranium dioxide journal November 2011
On the theory of fission gas bubble evolution in irradiated UO2 fuel journal January 2000
Stereological evolution of the rim structure in PWR-fuels at prolonged irradiation: Dependencies with burn-up and temperature journal August 2006
The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material journal December 1959
Nearest-neighbor distribution functions in many-body systems journal February 1990
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS journal April 2017
High resolution TEM of high burnup UO2 fuel journal December 1997
A model for bubble diffusion in uranium dioxide journal October 1981
Unit mechanisms of fission gas release: Current understanding and future needs journal June 2018
Characterization of Low-Gas-Release LHR Fuels by Transmission Electron Microscopy journal January 1988
Gas release mechanisms in UO 2 —a critical review journal January 1980
On the effect of irradiation-induced resolution in modelling fission gas release in UO 2 LWR fuel journal December 2017
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling journal January 2015
Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions journal October 1997
A review of fuel performance modelling journal April 2019
On the behaviour of intragranular fission gas in UO2 fuel journal June 2000
Local fission gas release and swelling in water reactor fuel during slow power transients journal April 1985
An equation of state for xenon/krypton mixtures confined in the nuclear fuels journal March 2020
Theory of diffusion-limited precipitation journal September 1958
Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO2 journal November 2015
A simulation study of ostwald ripening of gas bubbles in metals accounting for real gas behaviour journal August 1991
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions journal August 2019
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes journal April 2020
Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases journal June 1998
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools journal April 2018
Modelling intra-granular bubble movement and fission gas release during post-irradiation annealing of UO2 using a meso-scale and spatialized approach journal January 2020

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