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Title: A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels

Authors:
; ; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1532427
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Name: Journal of Nuclear Materials Journal Volume: 524 Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Frazier, William E., Hu, Shenyang, Burkes, Douglas E., and Beeler, Benjamin W. A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels. Netherlands: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.07.004.
Frazier, William E., Hu, Shenyang, Burkes, Douglas E., & Beeler, Benjamin W. A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels. Netherlands. doi:https://doi.org/10.1016/j.jnucmat.2019.07.004
Frazier, William E., Hu, Shenyang, Burkes, Douglas E., and Beeler, Benjamin W. Tue . "A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels". Netherlands. doi:https://doi.org/10.1016/j.jnucmat.2019.07.004.
@article{osti_1532427,
title = {A Monte Carlo model of irradiation-induced recrystallization in polycrystalline UMo fuels},
author = {Frazier, William E. and Hu, Shenyang and Burkes, Douglas E. and Beeler, Benjamin W.},
abstractNote = {},
doi = {10.1016/j.jnucmat.2019.07.004},
journal = {Journal of Nuclear Materials},
number = C,
volume = 524,
place = {Netherlands},
year = {2019},
month = {10}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: https://doi.org/10.1016/j.jnucmat.2019.07.004

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Cited by: 1 work
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Works referenced in this record:

Physical properties of monolithic U8wt.%–Mo
journal, July 2010


A First-Passage Kinetic Monte Carlo algorithm for complex diffusion–reaction systems
journal, May 2010

  • Donev, Aleksandar; Bulatov, Vasily V.; Oppelstrup, Tomas
  • Journal of Computational Physics, Vol. 229, Issue 9
  • DOI: 10.1016/j.jcp.2009.12.038

Thermal compatibility studies of unirradiated UMo alloys dispersed in aluminum
journal, November 1997


Mesoscale model for fission-induced recrystallization in U-7Mo alloy
journal, November 2016


IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL
journal, April 2014

  • Meyer, M. K.; Gan, J.; Jue, J. F.
  • Nuclear Engineering and Technology, Vol. 46, Issue 2
  • DOI: 10.5516/NET.07.2014.706

Radiation-induced microstructural change in high burnup UO2 fuel pellets
journal, June 1994

  • Nogita, K.; Une, K.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 91, Issue 1-4
  • DOI: 10.1016/0168-583X(94)96235-9

Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels
journal, February 2000


Hot-isostatic pressing of U-10Zr by a coupled grain boundary diffusion and creep cavitation mechanism
journal, March 1996


Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002


Formation mechanism of gas bubble superlattice in UMo metal fuels: Phase-field modeling investigation
journal, October 2016


On the rim effect in high burnup UO2LWR fuels
journal, July 1992


Abnormal grain growth in the Potts model incorporating grain boundary complexion transitions that increase the mobility of individual boundaries
journal, September 2015


Towards the mathematical model of rim structure formation
journal, September 1997


Quantitative analysis of grain boundary properties in a generalized phase field model for grain growth in anisotropic systems
journal, July 2008


TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities
journal, May 2012


Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40–67 GWd/tM
journal, August 1996


High burn-up structure of U(Mo) dispersion fuel
journal, August 2016


Microstructural analysis of LWR spent fuels at high burnup
journal, June 1992


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


Atomistic simulations of thermodynamic properties of Xe gas bubbles in U10Mo fuels
journal, July 2017


High burn-up rim structure: evidences that xenon-depletion, pore formation and grain subdivision start at different local burn-ups
journal, August 1998


First-passage time approach to kinetic Monte Carlo simulations of metal (100) growth
journal, June 2010


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


Kinetics of the Q -State Potts Model in Two Dimensions
journal, January 1983

  • Sahni, Paramdeep S.; Grest, Gary S.; Anderson, Michael P.
  • Physical Review Letters, Vol. 50, Issue 4
  • DOI: 10.1103/PhysRevLett.50.263

Thermal properties of U–Mo alloys irradiated to moderate burnup and power
journal, September 2015


Effect of grain morphology on gas bubble swelling in UMo fuels – A 3D microstructure dependent Booth model
journal, November 2016


Phase-field modeling of gas bubbles and thermal conductivity evolution in nuclear fuels
journal, July 2009


Simulation and theory of abnormal grain growth—anisotropic grain boundary energies and mobilities
journal, April 1989


On abnormal subgrain growth and the origin of recrystallization nuclei
journal, May 2003


Recrystallization and fission-gas-bubble swelling of U–Mo fuel
journal, May 2013


Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors
journal, May 1984

  • Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard
  • Nuclear Technology, Vol. 65, Issue 2
  • DOI: 10.13182/NT84-A33408

Fission product induced swelling of U–Mo alloy fuel
journal, December 2011