Journal Articles using Bison

Papers by the Bison Team

J.A. Hirschhorn, L.K. Aagesen, C. Jiang, and G.L. Beausoleil. Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nuclear Engineering and Design, 432:113811, 2025. doi:10.1016/j.nucengdes.2024.113811.

@article{HIRSCHHORN2025113811,
    author = "Hirschhorn, J.A. and Aagesen, L.K. and Jiang, C. and Beausoleil, G.L.",
    title = "Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels",
    journal = "Nuclear Engineering and Design",
    volume = "432",
    pages = "113811",
    year = "2025",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2024.113811"
}

Jacob A. Hirschhorn, Mustafa K. Jaradat, Ryan T. Sweet, Paul A. Demkowicz, Paolo Balestra, and Gerhard Strydom. Development and demonstration of a bison-griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility. Nuclear Engineering and Design, 431:113720, 2025. doi:10.1016/j.nucengdes.2024.113720.

@article{HIRSCHHORN2025113720,
    author = "Hirschhorn, Jacob A. and Jaradat, Mustafa K. and Sweet, Ryan T. and Demkowicz, Paul A. and Balestra, Paolo and Strydom, Gerhard",
    title = "Development and demonstration of a BISON-Griffin modeling framework for the design of targeted {TRISO} transient experiments in the {T}ransient {R}eactor {T}est {F}acility",
    journal = "Nuclear Engineering and Design",
    volume = "431",
    pages = "113720",
    year = "2025",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2024.113720"
}

R.T. Sweet, C.P. Massey, J.A. Hirschhorn, S.B. Bell, and K.A. Kane. Wrought FeCrAl alloy (C26M) cladding behavior and burst under simulated loss-of-coolant accident conditions. Nuclear Engineering and Design, 431:113712, 2025. doi:10.1016/j.nucengdes.2024.113712.

@article{SWEET2025113712,
    author = "Sweet, R.T. and Massey, C.P. and Hirschhorn, J.A. and Bell, S.B. and Kane, K.A.",
    title = "Wrought {F}e{C}r{A}l alloy ({C26M}) cladding behavior and burst under simulated loss-of-coolant accident conditions",
    journal = "Nuclear Engineering and Design",
    volume = "431",
    pages = "113712",
    year = "2025",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2024.113712"
}

Nairi Baghdasaryan, Wen Jiang, Jason Hales, Tomasz Kozlowski, and Zuzanna Krajewska. Triso fuel performance analysis: uncertainty quantification toward optimization. Nuclear Engineering and Design, 410:112401, 2023. doi:10.1016/j.nucengdes.2023.112401.

@article{BAGHDASARYAN2023112401,
    author = "Baghdasaryan, Nairi and Jiang, Wen and Hales, Jason and Kozlowski, Tomasz and Krajewska, Zuzanna",
    title = "TRISO fuel performance analysis: Uncertainty quantification toward optimization",
    journal = "Nuclear Engineering and Design",
    volume = "410",
    pages = "112401",
    year = "2023",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2023.112401"
}

A. Toptan, W. Jiang, J. D. Hales, B. W. Spencer, and S. Novascone. Verification of Bison fission product species conservation under TRISO reactor conditions. Journal of Nuclear Materials, 573:154105, 2023. doi:10.1016/j.jnucmat.2022.154105.

@article{TOPTAN2023154105,
    author = "Toptan, A. and Jiang, W. and Hales, J. D. and Spencer, B. W. and Novascone, S.",
    title = "Verification of {B}ison fission product species conservation under {TRISO} reactor conditions",
    journal = "Journal of Nuclear Materials",
    volume = "573",
    pages = "154105",
    doi = "10.1016/j.jnucmat.2022.154105",
    year = "2023"
}

Antonio Recuero, Alexander Lindsay, and Dewen Yushu. An approach to grid-to-rod fretting wear modeling using dynamic mortar contact. Progress in Nuclear Energy, 163:104793, 2023. doi:10.1016/j.pnucene.2023.104793.

@article{RECUERO2023104793,
    author = "Recuero, Antonio and Lindsay, Alexander and Yushu, Dewen",
    title = "An approach to grid-to-rod fretting wear modeling using dynamic mortar contact",
    journal = "Progress in Nuclear Energy",
    volume = "163",
    pages = "104793",
    year = "2023",
    issn = "0149-1970",
    doi = "10.1016/j.pnucene.2023.104793"
}

Somayajulu L.N. Dhulipala, Michael D. Shields, Promit Chakroborty, Wen Jiang, Benjamin W. Spencer, Jason D. Hales, Vincent M. Labouré, Zachary M. Prince, Chandrakanth Bolisetti, and Yifeng Che. Reliability estimation of an advanced nuclear fuel using coupled active learning, multifidelity modeling, and subset simulation. Reliability Engineering & System Safety, 226:108693, 2022. doi:10.1016/j.ress.2022.108693.

@article{DHULIPALA2022108693,
    author = "Dhulipala, Somayajulu L.N. and Shields, Michael D. and Chakroborty, Promit and Jiang, Wen and Spencer, Benjamin W. and Hales, Jason D. and Labouré, Vincent M. and Prince, Zachary M. and Bolisetti, Chandrakanth and Che, Yifeng",
    title = "Reliability estimation of an advanced nuclear fuel using coupled active learning, multifidelity modeling, and subset simulation",
    journal = "Reliability Engineering \& System Safety",
    volume = "226",
    pages = "108693",
    year = "2022",
    issn = "0951-8320",
    doi = "10.1016/j.ress.2022.108693"
}

K.A. Gamble, B.W. Spencer, J.D. Hales, T.W. Knight, and E. Roberts. A layered 2d computational framework: theory and applications to nuclear fuel behavior. Nuclear Engineering and Design, 395:111847, 2022. doi:10.1016/j.nucengdes.2022.111847.

@article{GAMBLE2022111847,
    author = "Gamble, K.A. and Spencer, B.W. and Hales, J.D. and Knight, T.W. and Roberts, E.",
    title = "A layered 2D computational framework: Theory and applications to nuclear fuel behavior",
    journal = "Nuclear Engineering and Design",
    volume = "395",
    pages = "111847",
    year = "2022",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2022.111847"
}

A. Recuero, A. Lindsay, D. Yushu, J. W. Peterson, and B. Spencer. A mortar thermomechanical contact computational framework for nuclear fuel performance simulation. Nuclear Engineering and Design, 394:111808, 2022. doi:10.1016/j.nucengdes.2022.111808.

@article{RECUERO2022111808,
    author = "Recuero, A. and Lindsay, A. and Yushu, D. and Peterson, J. W. and Spencer, B.",
    title = "A mortar thermomechanical contact computational framework for nuclear fuel performance simulation",
    journal = "Nuclear Engineering and Design",
    volume = "394",
    pages = "111808",
    year = "2022",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2022.111808"
}

A. Toptan, N. Porter, J. D. Hales, W. Jiang, B. W. Spencer, and S. R. Novascone. Verification of MOOSE/Bison's heat conduction solver using combined spatiotemporal convergence analysis. ASME Journal of Verification, Validation and Uncertainty Quantification, 7(2):021006, 2022. doi:10.1115/1.4054216.

@article{TOPTAN2022021006,
    author = "Toptan, A. and Porter, N. and Hales, J. D. and Jiang, W. and Spencer, B. W. and Novascone, S. R.",
    title = "Verification of {MOOSE/Bison's} heat conduction solver using combined spatiotemporal convergence analysis",
    journal = "ASME Journal of Verification, Validation and Uncertainty Quantification",
    volume = "7",
    number = "2",
    pages = "021006",
    issn = "2377-2158",
    doi = "10.1115/1.4054216",
    year = "2022"
}

P.-C.A. Simon, L. K. Aagesen, C. Jiang, W. Jiang, and J.-H. Ke. Mechanistic calculation of the effective silver diffusion coefficient in polycrystalline silicon carbide: application to silver release in AGR-1 TRISO particles. Journal of Nuclear Materials, 563:153669, 2022. doi:10.1016/j.jnucmat.2022.153669.

@article{SIMON2022153669,
    author = "Simon, P.-C.A. and Aagesen, L. K. and Jiang, C. and Jiang, W. and Ke, J.-H.",
    title = "Mechanistic calculation of the effective silver diffusion coefficient in polycrystalline silicon carbide: Application to silver release in {AGR-1 TRISO} particles",
    journal = "Journal of Nuclear Materials",
    volume = "563",
    pages = "153669",
    year = "2022",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2022.153669"
}

S.L.N. Dhulipala, W. Jiang, B. W. Spencer, J. D. Hales, M. D. Shields, A. E. Slaughter, Z. M. Prince, V. M. Labouré, C. Bolisetti, and P. Chakroborty. Accelerated statistical failure analysis of multifidelity triso fuel models. Journal of Nuclear Materials, 563:153604, 2022. doi:10.1016/j.jnucmat.2022.153604.

@article{DHULIPALA2022153604,
    author = "Dhulipala, S.L.N. and Jiang, W. and Spencer, B. W. and Hales, J. D. and Shields, M. D. and Slaughter, A. E. and Prince, Z. M. and Labour\'{e}, V. M. and Bolisetti, C. and Chakroborty, P.",
    title = "Accelerated statistical failure analysis of multifidelity TRISO fuel models",
    journal = "Journal of Nuclear Materials",
    volume = "563",
    pages = "153604",
    doi = "10.1016/j.jnucmat.2022.153604",
    year = "2022"
}

F. Passelaigue, P.-C. A. Simon, and A. T. Motta. Predicting the hydride rim by improving the solubility limits in the Hydride Nucleation-Growth-Dissolution (HNGD) model. Journal of Nuclear Materials, 558:153363, 2022. doi:10.1016/j.jnucmat.2021.153363.

@article{PASSELAIGUE2022153363,
    author = "Passelaigue, F. and Simon, P.-C. A. and Motta, A. T.",
    title = "Predicting the hydride rim by improving the solubility limits in the {Hydride Nucleation-Growth-Dissolution (HNGD)} model",
    journal = "Journal of Nuclear Materials",
    volume = "558",
    pages = "153363",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2021.153363",
    year = "2022"
}

W. Jiang, G. Singh, J. D. Hales, A. Toptan, B. W. Spencer, S. R. Novascone, S. L. N. Dhulipala, and Z. M. Prince. Efficient high-fidelity TRISO statistical failure analysis using Bison: Applications to AGR-2 irradiation testing. Journal of Nuclear Materials, 562:153585, 2022. doi:10.1016/j.jnucmat.2022.153585.

@article{JIANG2022153585,
    author = "Jiang, W. and Singh, G. and Hales, J. D. and Toptan, A. and Spencer, B. W. and Novascone, S. R. and Dhulipala, S. L. N. and Prince, Z. M.",
    title = "Efficient high-fidelity {TRISO} statistical failure analysis using {Bison: A}pplications to {AGR-2} irradiation testing",
    journal = "Journal of Nuclear Materials",
    volume = "562",
    pages = "153585",
    doi = "10.1016/j.jnucmat.2022.153585",
    year = "2022"
}

X.-Y. Liu, C. Matthews, W. Jiang, M.W.D. Cooper, J.D. Hales, and D.A. Andersson. Atomistic and cluster dynamics modeling of fission gas (xe) diffusivity in triso fuel kernels. Journal of Nuclear Materials, 561:153539, 2022. doi:10.1016/j.jnucmat.2022.153539.

@article{LIU2022153539,
    author = "Liu, X.-Y. and Matthews, C. and Jiang, W. and Cooper, M.W.D. and Hales, J.D. and Andersson, D.A.",
    title = "Atomistic and cluster dynamics modeling of fission gas (Xe) diffusivity in TRISO fuel kernels",
    journal = "Journal of Nuclear Materials",
    volume = "561",
    pages = "153539",
    year = "2022",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2022.153539"
}

Karen E. Wright, John Stempien, Wen Jiang, and Isabella J. van Rooyen. Fission product distribution in irradiated safety-tested and as-irradiated AGR-2 TRISO particles. Journal of Nuclear Materials, 559:153468, 2022. doi:10.1016/j.jnucmat.2021.153468.

@article{WRIGHT2022153468,
    author = "Wright, Karen E. and Stempien, John and Jiang, Wen and {van Rooyen}, Isabella J.",
    title = "Fission product distribution in irradiated safety-tested and as-irradiated {AGR-2 TRISO} particles",
    journal = "Journal of Nuclear Materials",
    volume = "559",
    pages = "153468",
    doi = "10.1016/j.jnucmat.2021.153468",
    year = "2022"
}

J.D. Hales, A. Toptan, W. Jiang, and B.W. Spencer. Numerical evaluation of AGR-2 fission product release. Journal of Nuclear Materials, 558:153325, 2022. doi:10.1016/j.jnucmat.2021.153325.

@article{HALES2022153325,
    author = "Hales, J.D. and Toptan, A. and Jiang, W. and Spencer, B.W.",
    title = "Numerical evaluation of {AGR-2} fission product release",
    journal = "Journal of Nuclear Materials",
    volume = "558",
    pages = "153325",
    year = "2022",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2021.153325"
}

Ryan Sweet, Peter Mouche, Samuel Bell, Kenneth Kane, and Nathan Capps. Chromium-coated cladding analysis under simulated LOCA burst conditions. Annals of Nuclear Energy, 176:109275, 2022. doi:10.1016/j.anucene.2022.109275.

@article{SWEET2022109275,
    author = "Sweet, Ryan and Mouche, Peter and Bell, Samuel and Kane, Kenneth and Capps, Nathan",
    title = "{Chromium-coated cladding analysis under simulated LOCA burst conditions}",
    journal = "Annals of Nuclear Energy",
    volume = "176",
    pages = "109275",
    year = "2022",
    doi = "10.1016/j.anucene.2022.109275"
}

Jacob A. Hirschhorn, Jeffrey J. Powers, Ian Greenquist, Ryan T. Sweet, Jianwei Hu, Douglas L. Porter, and Douglas C. Crawford. Metallic fuel performance benchmarks for Versatile Test Reactor applications. Nuclear Science and Engineering, 196:S123–S147, 2022. doi:10.1080/00295639.2022.2043539.

@article{HIRSCHHORN2022S123,
    author = "Hirschhorn, Jacob A. and Powers, Jeffrey J. and Greenquist, Ian and Sweet, Ryan T. and Hu, Jianwei and Porter, Douglas L. and Crawford, Douglas C.",
    title = "{Metallic fuel performance benchmarks for Versatile Test Reactor applications}",
    journal = "Nuclear Science and Engineering",
    volume = "196",
    pages = "S123-S147",
    year = "2022",
    doi = "10.1080/00295639.2022.2043539"
}

Y. Miao, A. Oaks, K. Mo, M. Billone, C. Matthews, A. X. Zabriskie, S. Novascone, and A. M. Yacout. Metallic fuel cladding degradation model development and evaluation for BISON. Nuclear Engineering and Design, 385:111531, 2021. doi:10.1016/j.nucengdes.2021.111531.

@article{MIAO2021111531,
    author = "Miao, Y. and Oaks, A. and Mo, K. and Billone, M. and Matthews, C. and Zabriskie, A. X. and Novascone, S. and Yacout, A. M.",
    title = "Metallic fuel cladding degradation model development and evaluation for {BISON}",
    journal = "Nuclear Engineering and Design",
    volume = "385",
    pages = "111531",
    doi = "10.1016/j.nucengdes.2021.111531",
    year = "2021"
}

Louis Bailly-Salins, Léo Borrel, Wen Jiang, Benjamin W. Spencer, Koroush Shirvan, and Adrien Couet. Modeling of high-temperature corrosion of zirconium alloys using the extended finite element method (X-FEM). Corrosion Science, 189:109603, 2021. doi:10.1016/j.corsci.2021.109603.

@article{BAILLYSALINS2021109603,
    author = "Bailly-Salins, Louis and Borrel, L\'{e}o and Jiang, Wen and Spencer, Benjamin W. and Shirvan, Koroush and Couet, Adrien",
    title = "Modeling of High-Temperature Corrosion of Zirconium Alloys Using the eXtended Finite Element Method ({X-FEM})",
    journal = "Corrosion Science",
    volume = "189",
    pages = "109603",
    doi = "10.1016/j.corsci.2021.109603",
    year = "2021"
}

B. Collin, W. Jiang, K. Gamble, R. Gardner, J. Hales, B. Haugh, S. Novascone, J. Roche, B. Spencer, and A. Toptan. TRISO fuel performance modelling with BISON. Journal of Physics: Conference Series, 2048(1):012012, 2021. doi:10.1088/1742-6596/2048/1/012012.

@article{COLLIN2021012012,
    author = "Collin, B. and Jiang, W. and Gamble, K. and Gardner, R. and Hales, J. and Haugh, B. and Novascone, S. and Roche, J. and Spencer, B. and Toptan, A.",
    title = "{TRISO} Fuel Performance Modelling with {BISON}",
    journal = "Journal of Physics: Conference Series",
    publisher = "{IOP} Publishing",
    volume = "2048",
    number = "1",
    pages = "012012",
    doi = "10.1088/1742-6596/2048/1/012012",
    year = "2021"
}

K.A. Gamble, T.W. Knight, E. Roberts, J.D. Hales, and B.W. Spencer. Mechanistic verification of empirical UO$_2$ fuel fracture models. Journal of Nuclear Materials, 556:153163, 2021. doi:10.1016/j.jnucmat.2021.153163.

@article{GAMBLE2021153163,
    author = "Gamble, K.A. and Knight, T.W. and Roberts, E. and Hales, J.D. and Spencer, B.W.",
    title = "Mechanistic verification of empirical {UO$\_2$} fuel fracture models",
    journal = "Journal of Nuclear Materials",
    volume = "556",
    pages = "153163",
    year = "2021",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2021.153163"
}

Aysenur Toptan, Wen Jiang, Jason D. Hales, Benjamin W. Spencer, Albert Casagranda, and Stephen R. Novascone. FEA-aided investigation of the effective thermal conductivity in a medium with embedded spheres. Nuclear Engineering and Design, 381:111355, 2021. doi:10.1016/j.nucengdes.2021.111355.

@article{TOPTAN2021111355,
    author = "Toptan, Aysenur and Jiang, Wen and Hales, Jason D. and Spencer, Benjamin W. and Casagranda, Albert and Novascone, Stephen R.",
    title = "{FEA}-aided investigation of the effective thermal conductivity in a medium with embedded spheres",
    journal = "Nuclear Engineering and Design",
    pages = "111355",
    year = "2021",
    doi = "10.1016/j.nucengdes.2021.111355",
    volume = "381"
}

Jianguo Yu, Cole D. Blakely, Jason D. Hales, and Hongbin Zhang. Accident tolerant fuel rod failure under low stress: a case study of BWR under station blackout using Bison. Journal of Nuclear Materials, pages 153037, 2021. doi:10.1016/j.jnucmat.2021.153037.

@article{YU2021153037,
    author = "Yu, Jianguo and Blakely, Cole D. and Hales, Jason D. and Zhang, Hongbin",
    title = "Accident Tolerant Fuel Rod Failure Under Low Stress: A Case Study Of {BWR} Under Station Blackout Using {Bison}",
    journal = "Journal of Nuclear Materials",
    pages = "153037",
    year = "2021",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2021.153037"
}

Richard L. Williamson, Jason D. Hales, Stephen R. Novascone, Giovanni Pastore, Kyle A. Gamble, Benjamin W. Spencer, Wen Jiang, Stephanie A. Pitts, Albert Casagranda, Daniel Schwen, Adam X. Zabriskie, Aysenur Toptan, Russell Gardner, Christoper Matthews, Wenfeng Liu, and Hailong Chen. BISON: a flexible code for advanced simulation of the performance of multiple nuclear fuel forms. Nuclear Technology, 207(7):954–980, 2021. doi:10.1080/00295450.2020.1836940.

@article{WILLIAMSON2021954,
    author = "Williamson, Richard L. and Hales, Jason D. and Novascone, Stephen R. and Pastore, Giovanni and Gamble, Kyle A. and Spencer, Benjamin W. and Jiang, Wen and Pitts, Stephanie A. and Casagranda, Albert and Schwen, Daniel and Zabriskie, Adam X. and Toptan, Aysenur and Gardner, Russell and Matthews, Christoper and Liu, Wenfeng and Chen, Hailong",
    title = "{BISON}: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms",
    journal = "Nuclear Technology",
    volume = "207",
    number = "7",
    pages = "954-980",
    year = "2021",
    doi = "10.1080/00295450.2020.1836940"
}

Jason D. Hales, Wen Jiang, Aysenur Toptan, and Kyle A. Gamble. Modeling fission product diffusion in TRISO fuel particles with BISON. Journal of Nuclear Materials, 548:152840, 2021. doi:10.1016/j.jnucmat.2021.152840.

@article{HALES2021152840,
    author = "Hales, Jason D. and Jiang, Wen and Toptan, Aysenur and Gamble, Kyle A.",
    title = "Modeling fission product diffusion in {TRISO} fuel particles with {BISON}",
    journal = "Journal of Nuclear Materials",
    pages = "152840",
    volume = "548",
    year = "2021",
    doi = "10.1016/j.jnucmat.2021.152840"
}

Wen Jiang, Jason D. Hales, Benjamin W. Spencer, Blaise P. Collin, Andrew E. Slaughter, Stephen R. Novascone, Aysenur Toptan, Kyle A. Gamble, and Russell Gardner. TRISO particle fuel performance and failure analysis with BISON. Journal of Nuclear Materials, 548:152795, 2021. doi:10.1016/j.jnucmat.2021.152795.

@article{JIANG2021152795,
    author = "Jiang, Wen and Hales, Jason D. and Spencer, Benjamin W. and Collin, Blaise P. and Slaughter, Andrew E. and Novascone, Stephen R. and Toptan, Aysenur and Gamble, Kyle A. and Gardner, Russell",
    title = "{TRISO} Particle Fuel Performance and Failure Analysis with {BISON}",
    journal = "Journal of Nuclear Materials",
    volume = "548",
    pages = "152795",
    year = "2021",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2021.152795"
}

G. Pastore, R. L. Williamson, R. J. Gardner, S. R. Novascone, J. B. Tompkins, K. A. Gamble, and J. D. Hales. Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments. Journal of Nuclear Materials, 543:152537, 2021. doi:10.1016/j.jnucmat.2020.152537.

@article{PASTORE2021152537,
    author = "Pastore, G. and Williamson, R. L. and Gardner, R. J. and Novascone, S. R. and Tompkins, J. B. and Gamble, K. A. and Hales, J. D.",
    title = "Analysis of fuel rod behavior during loss-of-coolant accidents using the {BISON} code: {C}ladding modeling developments and simulation of separate-effects experiments",
    journal = "Journal of Nuclear Materials",
    pages = "152537",
    volume = "543",
    year = "2021",
    doi = "10.1016/j.jnucmat.2020.152537"
}

G. Pastore, K. A. Gamble, R. L. Williamson, S. R. Novascone, R. J. Gardner, and J. D. Hales. Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments. Journal of Nuclear Materials, 545:152645, 2021. doi:10.1016/j.jnucmat.2020.152645.

@article{PASTORE2021152645,
    author = "Pastore, G. and Gamble, K. A. and Williamson, R. L. and Novascone, S. R. and Gardner, R. J. and Hales, J. D.",
    title = "Analysis of fuel rod behavior during loss-of-coolant accidents using the {BISON} code: {F}uel modeling developments and simulation of integral experiments",
    journal = "Journal of Nuclear Materials",
    pages = "152645",
    volume = "545",
    year = "2021",
    doi = "10.1016/j.jnucmat.2020.152645"
}

Jacob Hirschhorn, Michael Tonks, and Christopher Matthews. A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON. Journal of Nuclear Materials, 544:152657, 2021. doi:10.1016/j.jnucmat.2020.152657.

@article{HIRSCHHORN2021152657,
    author = "Hirschhorn, Jacob and Tonks, Michael and Matthews, Christopher",
    doi = "10.1016/j.jnucmat.2020.152657",
    journal = "Journal of Nuclear Materials",
    publisher = "Elsevier",
    title = "{A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON}",
    volume = "544",
    pages = "152657",
    year = "2021"
}

Michael R. Tonks, Pierre-Clément A. Simon, and Jacob Hirschhorn. Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel. Journal of Nuclear Materials, 543:152576, 2021. doi:10.1016/j.jnucmat.2020.152576.

@article{TONKS2021152576,
    author = "Tonks, Michael R. and Simon, Pierre-Clément A. and Hirschhorn, Jacob",
    title = "{Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel}",
    journal = "Journal of Nuclear Materials",
    volume = "543",
    pages = "152576",
    year = "2021",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2020.152576"
}

Aysenur Toptan, Nathan W. Porter, Jason D. Hales, Benjamin W. Spencer, Martin Pilch, and Richard L. Williamson. Construction of a Code Verification Matrix for Heat Conduction With Finite Element Code Applications. Journal of Verification, Validation and Uncertainty Quantification, 5(4):041002, 12 2020. doi:10.1115/1.4049037.

@article{TOPTAN2020041002,
    author = "Toptan, Aysenur and Porter, Nathan W. and Hales, Jason D. and Spencer, Benjamin W. and Pilch, Martin and Williamson, Richard L.",
    title = "{Construction of a Code Verification Matrix for Heat Conduction With Finite Element Code Applications}",
    journal = "Journal of Verification, Validation and Uncertainty Quantification",
    volume = "5",
    number = "4",
    year = "2020",
    month = "12",
    issn = "2377-2158",
    doi = "10.1115/1.4049037",
    pages = "041002"
}

Aysenur Toptan, Jason D. Hales, Richard L. Williamson, Stephen R. Novascone, Giovanni Pastore, and David J. Kropaczek. Modeling of gap conductance for LWR fuel rods applied in the BISON code. Journal of Nuclear Science and Technology, 57(8):963–974, 2020. doi:10.1080/00223131.2020.1740808.

@article{TOPTAN2020963,
    author = "Toptan, Aysenur and Hales, Jason D. and Williamson, Richard L. and Novascone, Stephen R. and Pastore, Giovanni and Kropaczek, David J.",
    title = "Modeling of gap conductance for {LWR} fuel rods applied in the {BISON} code",
    journal = "Journal of Nuclear Science and Technology",
    year = "2020",
    volume = "57",
    number = "8",
    pages = "963--974",
    issn = "0022-3131",
    doi = "10.1080/00223131.2020.1740808"
}

Wen Jiang, Benjamin W. Spencer, and John E. Dolbow. Ceramic nuclear fuel fracture modeling with the extended finite element method. Engineering Fracture Mechanics, 223:106713, 2020. doi:10.1016/j.engfracmech.2019.106713.

@article{JIANG2020106713,
    author = "Jiang, Wen and Spencer, Benjamin W. and Dolbow, John E.",
    title = "Ceramic nuclear fuel fracture modeling with the extended finite element method",
    journal = "Engineering Fracture Mechanics",
    volume = "223",
    pages = "106713",
    year = "2020",
    issn = "0013-7944",
    doi = "10.1016/j.engfracmech.2019.106713"
}

R.T. Sweet, Y. Yang, K.A. Terrani, B.D. Wirth, and A.T. Nelson. Performance of U3Si2 in an LWR following a cladding breach during normal operation. Journal of Nuclear Materials, 539:152263, 2020. doi:10.1016/j.jnucmat.2020.152263.

@article{SWEET2020152263,
    author = "Sweet, R.T. and Yang, Y. and Terrani, K.A. and Wirth, B.D. and Nelson, A.T.",
    title = "{Performance of U3Si2 in an LWR following a cladding breach during normal operation}",
    journal = "Journal of Nuclear Materials",
    volume = "539",
    pages = "152263",
    year = "2020",
    doi = "10.1016/j.jnucmat.2020.152263"
}

T. Barani, G. Pastore, D. Pizzocri, D.A. Andersson, C. Matthews, A. Alfonsi, K.A. Gamble, P. Van Uffelen, L. Luzzi, and J.D. Hales. Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions. Journal of Nuclear Materials, 522:97 – 110, 2019. doi:10.1016/j.jnucmat.2019.04.037.

@article{BARANI201997,
    author = "Barani, T. and Pastore, G. and Pizzocri, D. and Andersson, D.A. and Matthews, C. and Alfonsi, A. and Gamble, K.A. and Uffelen, P. Van and Luzzi, L. and Hales, J.D.",
    title = "Multiscale modeling of fission gas behavior in {U3Si2} under {LWR} conditions",
    journal = "Journal of Nuclear Materials",
    volume = "522",
    pages = "97 - 110",
    year = "2019",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2019.04.037"
}

P. Van Uffelen, J. Hales, W. Li, G. Rossiter, and R. Williamson. A review of fuel performance modelling. Journal of Nuclear Materials, 516:373–412, 2019. doi:10.1016/j.jnucmat.2018.12.037.

@article{VANUFFELEN2019373,
    author = "Uffelen, P. Van and Hales, J. and Li, W. and Rossiter, G. and Williamson, R.",
    title = "A review of fuel performance modelling",
    journal = "Journal of Nuclear Materials",
    volume = "516",
    pages = "373-412",
    year = "2019",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2018.12.037"
}

T. Barani, D. Pizzocri, G. Pastore, L. Luzzi, and J.D. Hales. Isotropic softening model for fuel cracking in BISON. Nuclear Engineering and Design, 342:257–263, 2019. doi:10.1016/j.nucengdes.2018.12.005.

@article{BARANI2019257,
    author = "Barani, T. and Pizzocri, D. and Pastore, G. and Luzzi, L. and Hales, J.D.",
    title = "Isotropic softening model for fuel cracking in {BISON}",
    journal = "Nuclear Engineering and Design",
    volume = "342",
    pages = "257-263",
    year = "2019",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2018.12.005"
}

Yifeng Che, Giovanni Pastore, Jason Hales, and Koroush Shirvan. Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337:271–278, 2018. doi:10.1016/j.nucengdes.2018.07.015.

@article{CHE2018271,
    author = "Che, Yifeng and Pastore, Giovanni and Hales, Jason and Shirvan, Koroush",
    title = "Modeling of {Cr2O3}-doped {UO2} as a near-term accident tolerant fuel for {LWRs} using the {BISON} code",
    journal = "Nuclear Engineering and Design",
    volume = "337",
    pages = "271-278",
    year = "2018",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2018.07.015"
}

Malik Wagih, Benjamin Spencer, Jason Hales, and Koroush Shirvan. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120:304–318, 2018. doi:10.1016/j.anucene.2018.06.001.

@article{WAGIH2018304,
    author = "Wagih, Malik and Spencer, Benjamin and Hales, Jason and Shirvan, Koroush",
    title = "Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings",
    journal = "Annals of Nuclear Energy",
    volume = "120",
    pages = "304-318",
    year = "2018",
    issn = "0306-4549",
    doi = "10.1016/j.anucene.2018.06.001"
}

S. Novascone, P. Medvedev, J.W. Peterson, Y. Zhang, and J. Hales. Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method. Journal of Nuclear Materials, 508:226–236, 2018. doi:10.1016/j.jnucmat.2018.05.041.

@article{NOVASCONE2018226,
    author = "Novascone, S. and Medvedev, P. and Peterson, J.W. and Zhang, Y. and Hales, J.",
    title = "Modeling porosity migration in {LWR} and fast reactor {MOX} fuel using the finite element method",
    journal = "Journal of Nuclear Materials",
    volume = "508",
    pages = "226-236",
    year = "2018",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2018.05.041"
}

D. Pizzocri, G. Pastore, T. Barani, A. Magni, L. Luzzi, P. Van Uffelen, S.A. Pitts, A. Alfonsi, and J.D. Hales. A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools. Journal of Nuclear Materials, 502:323 – 330, 2018. doi:10.1016/j.jnucmat.2018.02.024.

@article{PIZZOCRI2018323,
    author = "Pizzocri, D. and Pastore, G. and Barani, T. and Magni, A. and Luzzi, L. and Uffelen, P. Van and Pitts, S.A. and Alfonsi, A. and Hales, J.D.",
    title = "A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools",
    journal = "Journal of Nuclear Materials",
    year = "2018",
    volume = "502",
    pages = "323 - 330",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2018.02.024"
}

R.T. Sweet, N.M. George, G.I. Maldonado, K.A. Terrani, and B.D. Wirth. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation. Nuclear Engineering and Design, 328:10–26, 2018. doi:10.1016/j.nucengdes.2017.11.043.

@article{SWEET201810,
    author = "Sweet, R.T. and George, N.M. and Maldonado, G.I. and Terrani, K.A. and Wirth, B.D.",
    title = "{Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation}",
    journal = "Nuclear Engineering and Design",
    volume = "328",
    pages = "10-26",
    year = "2018",
    doi = "10.1016/j.nucengdes.2017.11.043"
}

K.A. Gamble, T. Barani, D. Pizzocri, J.D. Hales, K.A. Terrani, and G. Pastore. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions. Journal of Nuclear Materials, 491:55–66, 2017. doi:10.1016/j.jnucmat.2017.04.039.

@article{GAMBLE201755,
    author = "Gamble, K.A. and Barani, T. and Pizzocri, D. and Hales, J.D. and Terrani, K.A. and Pastore, G.",
    title = "An investigation of {FeCrAl} cladding behavior under normal operating and loss of coolant conditions",
    journal = "Journal of Nuclear Materials",
    volume = "491",
    pages = "55-66",
    year = "2017",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2017.04.039"
}

B.W. Spencer, R.L. Williamson, D.S. Stafford, S.R. Novascone, J.D. Hales, and G. Pastore. 3D modeling of missing pellet surface defects in BWR fuel. Nuclear Engineering and Design, 307:155–171, 2016. doi:10.1016/j.nucengdes.2016.07.008.

@article{SPENCER2016155,
    author = "Spencer, B.W. and Williamson, R.L. and Stafford, D.S. and Novascone, S.R. and Hales, J.D. and Pastore, G.",
    title = "{3D} modeling of missing pellet surface defects in {BWR} fuel",
    journal = "Nuclear Engineering and Design",
    volume = "307",
    pages = "155-171",
    year = "2016",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2016.07.008"
}

R.L. Williamson, K.A. Gamble, D.M. Perez, S.R. Novascone, G. Pastore, R.J. Gardner, J.D. Hales, W. Liu, and A. Mai. Validating the BISON fuel performance code to integral LWR experiments. Nuclear Engineering and Design, 301:232–244, 2016. doi:10.1016/j.nucengdes.2016.02.020.

@article{WILLIAMSON2016232,
    author = "Williamson, R.L. and Gamble, K.A. and Perez, D.M. and Novascone, S.R. and Pastore, G. and Gardner, R.J. and Hales, J.D. and Liu, W. and Mai, A.",
    title = "Validating the {BISON} fuel performance code to integral {LWR} experiments",
    journal = "Nuclear Engineering and Design",
    volume = "301",
    pages = "232-244",
    year = "2016",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2016.02.020"
}

S.R. Novascone, B.W. Spencer, J.D. Hales, and R.L. Williamson. Evaluation of coupling approaches for thermomechanical simulations. Nuclear Engineering and Design, 295:910–921, 2015. doi:10.1016/j.nucengdes.2015.07.005.

@article{NOVASCONE2015910,
    author = "Novascone, S.R. and Spencer, B.W. and Hales, J.D. and Williamson, R.L.",
    title = "Evaluation of coupling approaches for thermomechanical simulations",
    journal = "Nuclear Engineering and Design",
    volume = "295",
    pages = "910-921",
    year = "2015",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2015.07.005"
}

Xu Wu, Tomasz Kozlowski, and Jason D. Hales. Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions. Annals of Nuclear Energy, 85:763–775, 2015. doi:10.1016/j.anucene.2015.06.032.

@article{WU2015763,
    author = "Wu, Xu and Kozlowski, Tomasz and Hales, Jason D.",
    title = "Neutronics and fuel performance evaluation of accident tolerant {FeCrAl} cladding under normal operation conditions",
    journal = "Annals of Nuclear Energy",
    volume = "85",
    pages = "763-775",
    year = "2015",
    issn = "0306-4549",
    doi = "10.1016/j.anucene.2015.06.032"
}

D.S. Stafford. Multidimensional simulations of hydrides during fuel rod lifecycle. Journal of Nuclear Materials, 466:362–372, 2015. doi:10.1016/j.jnucmat.2015.06.037.

@article{STAFFORD2015362,
    author = "Stafford, D.S.",
    title = "Multidimensional simulations of hydrides during fuel rod lifecycle",
    journal = "Journal of Nuclear Materials",
    volume = "466",
    pages = "362-372",
    year = "2015",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2015.06.037"
}

J. D. Hales, M. R. Tonks, K. Chockalingam, D. M. Perez, S. R. Novascone, B. W. Spencer, and R. L. Williamson. Asymptotic expansion homogenization for multiscale nuclear fuel analysis. Computational Materials Science, 99:290–297, March 2015. URL: http://dx.doi.org/10.1016/j.commatsci.2014.12.039, doi:10.1016/j.commatsci.2014.12.039.

@Article{hales15homogenization,
    author = "Hales, J. D. and Tonks, M. R. and Chockalingam, K. and Perez, D. M. and Novascone, S. R. and Spencer, B. W. and Williamson, R. L.",
    title = "Asymptotic expansion homogenization for multiscale nuclear fuel analysis",
    journal = "Computational Materials Science",
    year = "2015",
    volume = "99",
    month = "March",
    pages = "290--297",
    doi = "10.1016/j.commatsci.2014.12.039",
    url = "http://dx.doi.org/10.1016/j.commatsci.2014.12.039"
}

J.D. Hales, M.R. Tonks, F.N. Gleicher, B.W. Spencer, S.R. Novascone, R.L. Williamson, G. Pastore, and D.M. Perez. Advanced multiphysics coupling for LWR fuel performance analysis. Annals of Nuclear Energy, 84:98–110, 2015. Multi-Physics Modelling of LWR Static and Transient Behaviour. doi:10.1016/j.anucene.2014.11.003.

@article{HALES201598,
    author = "Hales, J.D. and Tonks, M.R. and Gleicher, F.N. and Spencer, B.W. and Novascone, S.R. and Williamson, R.L. and Pastore, G. and Perez, D.M.",
    title = "Advanced multiphysics coupling for {LWR} fuel performance analysis",
    journal = "Annals of Nuclear Energy",
    volume = "84",
    pages = "98-110",
    year = "2015",
    note = "Multi-Physics Modelling of LWR Static and Transient Behaviour",
    issn = "0306-4549",
    doi = "10.1016/j.anucene.2014.11.003"
}

Giovanni Pastore, L.P. Swiler, J.D. Hales, S.R. Novascone, D.M. Perez, B.W. Spencer, L. Luzzi, P. Van Uffelen, and R.L. Williamson. Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling. Journal of Nuclear Materials, 456:398–408, 2015. doi:10.1016/j.jnucmat.2014.09.077.

@article{PASTORE2015398,
    author = "Pastore, Giovanni and Swiler, L.P. and Hales, J.D. and Novascone, S.R. and Perez, D.M. and Spencer, B.W. and Luzzi, L. and {Van Uffelen}, P. and Williamson, R.L.",
    title = "Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling",
    journal = "Journal of Nuclear Materials",
    volume = "456",
    pages = "398-408",
    year = "2015",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2014.09.077"
}

H. Huang, B. Spencer, and J. Hales. Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets. Nuclear Engineering and Design, 278:515–528, 2014. doi:10.1016/j.nucengdes.2014.05.049.

@article{HUANG2014515,
    author = "Huang, H. and Spencer, B. and Hales, J.",
    title = "Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets",
    journal = "Nuclear Engineering and Design",
    volume = "278",
    pages = "515-528",
    year = "2014",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2014.05.049"
}

Olivier Courty, Arthur T. Motta, and Jason D. Hales. Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding. Journal of Nuclear Materials, 452(1):311–320, 2014. doi:10.1016/j.jnucmat.2014.05.013.

@article{COURTY2014311,
    author = "Courty, Olivier and Motta, Arthur T. and Hales, Jason D.",
    title = "Modeling and simulation of hydrogen behavior in {Z}ircaloy-4 fuel cladding",
    journal = "Journal of Nuclear Materials",
    volume = "452",
    number = "1",
    pages = "311-320",
    year = "2014",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2014.05.013"
}

J.D. Hales, S.R. Novascone, B.W. Spencer, R.L. Williamson, G. Pastore, and D.M. Perez. Verification of the BISON fuel performance code. Annals of Nuclear Energy, 71:81–90, 2014. doi:10.1016/j.anucene.2014.03.027.

@article{HALES201481,
    author = "Hales, J.D. and Novascone, S.R. and Spencer, B.W. and Williamson, R.L. and Pastore, G. and Perez, D.M.",
    title = "Verification of the {BISON} fuel performance code",
    journal = "Annals of Nuclear Energy",
    volume = "71",
    pages = "81-90",
    year = "2014",
    issn = "0306-4549",
    doi = "10.1016/j.anucene.2014.03.027"
}

M. Teague, M. Tonks, S. Novascone, and S. Hayes. Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1):161–169, 2014. doi:10.1016/j.jnucmat.2013.09.035.

@article{TEAGUE2014161,
    author = "Teague, M. and Tonks, M. and Novascone, S. and Hayes, S.",
    title = "Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel",
    journal = "Journal of Nuclear Materials",
    volume = "444",
    number = "1",
    pages = "161-169",
    year = "2014",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2013.09.035"
}

J.D. Hales, R.L. Williamson, S.R. Novascone, D.M. Perez, B.W. Spencer, and G. Pastore. Multidimensional multiphysics simulation of TRISO particle fuel. Journal of Nuclear Materials, 443(1):531–543, 2013. doi:10.1016/j.jnucmat.2013.07.070.

@article{HALES2013531,
    author = "Hales, J.D. and Williamson, R.L. and Novascone, S.R. and Perez, D.M. and Spencer, B.W. and Pastore, G.",
    title = "Multidimensional multiphysics simulation of {TRISO} particle fuel",
    journal = "Journal of Nuclear Materials",
    volume = "443",
    number = "1",
    pages = "531-543",
    year = "2013",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2013.07.070"
}

M.R. Tonks, P.C. Millett, P. Nerikar, S. Du, D. Andersson, C.R. Stanek, D. Gaston, D. Andrs, and R. Williamson. Multiscale development of a fission gas thermal conductivity model: coupling atomic, meso and continuum level simulations. Journal of Nuclear Materials, 440(1):193–200, 2013. doi:10.1016/j.jnucmat.2013.05.008.

@article{TONKS2013193,
    author = "Tonks, M.R. and Millett, P.C. and Nerikar, P. and Du, S. and Andersson, D. and Stanek, C.R. and Gaston, D. and Andrs, D. and Williamson, R.",
    title = "Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations",
    journal = "Journal of Nuclear Materials",
    volume = "440",
    number = "1",
    pages = "193-200",
    year = "2013",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2013.05.008"
}

R.L. Williamson, J.D. Hales, S.R. Novascone, M.R. Tonks, D.R. Gaston, C.J. Permann, D. Andrs, and R.C. Martineau. Multidimensional multiphysics simulation of nuclear fuel behavior. Journal of Nuclear Materials, 423(1):149–163, 2012. doi:10.1016/j.jnucmat.2012.01.012.

@article{WILLIAMSON2012149,
    author = "Williamson, R.L. and Hales, J.D. and Novascone, S.R. and Tonks, M.R. and Gaston, D.R. and Permann, C.J. and Andrs, D. and Martineau, R.C.",
    title = "Multidimensional multiphysics simulation of nuclear fuel behavior",
    journal = "Journal of Nuclear Materials",
    volume = "423",
    number = "1",
    pages = "149-163",
    year = "2012",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2012.01.012"
}

J. D. Hales, S. R. Novascone, R. L. Williamson, D. R. Gaston, and M. R. Tonks. Solving nonlinear solid mechanics problems with the Jacobian-free Newton Krylov method. Computer Modeling in Engineering and Sciences, 84(2):123–154, 2012. doi:10.3970/cmes.2012.084.123.

@article{HALES2012123,
    author = "Hales, J. D. and Novascone, S. R. and Williamson, R. L. and Gaston, D. R. and Tonks, M. R.",
    journal = "Computer Modeling in Engineering and Sciences",
    volume = "84",
    number = "2",
    pages = "123-154",
    title = "Solving Nonlinear Solid Mechanics Problems with the {J}acobian-Free {N}ewton {K}rylov Method",
    doi = "10.3970/cmes.2012.084.123",
    year = "2012"
}

K. Chockalingam, M. R. Tonks, J. D. Hales, D. R. Gaston, P. C. Millett, and L. Zhang. Crystal plasticity with Jacobian-free Newton–Krylov. Computational Mechanics, 51:617–627, 2013. doi:10.1007/s00466-012-0741-7.

@article{CHOCKALINGAM2013617,
    author = "Chockalingam, K. and Tonks, M. R. and Hales, J. D. and Gaston, D. R. and Millett, P. C. and Zhang, L.",
    title = "Crystal plasticity with {J}acobian-Free {N}ewton--{K}rylov",
    journal = "Computational Mechanics",
    pages = "617-627",
    year = "2013",
    volume = "51",
    publisher = "Springer",
    doi = "10.1007/s00466-012-0741-7"
}

D. Gaston, L. Guo, G. Hansen, H. Huang, R. Johnson, H.K. Park, R. Podgorney, M. Tonks, and R. Williamson. Parallel algorithms and software for nuclear, energy, and environmental applications. Part I: Multiphysics algorithms. Communications in Computational Physics, 12(3):807–833, 2012. doi:10.4208/cicp.091010.140711s.

@article{HANSEN2012807,
    author = "Gaston, D. and Guo, L. and Hansen, G. and Huang, H. and Johnson, R. and Park, H.K. and Podgorney, R. and Tonks, M. and Williamson, R.",
    title = "Parallel Algorithms and Software for Nuclear, Energy, and Environmental Applications. {Part I: M}ultiphysics Algorithms",
    journal = "Communications in Computational Physics",
    volume = "12",
    number = "3",
    comment = "INL/JOU-10-20006",
    year = "2012",
    Pages = "807-833",
    publisher = "Idaho National Laboratory (INL)",
    doi = "10.4208/cicp.091010.140711s"
}

D. Gaston, L. Guo, G. Hansen, H. Huang, R. Johnson, D. Knoll, C. Newman, H.K. Park, R. Podgorney, M. Tonks, and R. Williamson. Parallel algorithms and software for nuclear, energy, and environmental applications. Part II: Multiphysics software. Communications in Computational Physics, 12(3):834–865, 2012. doi:10.4208/cicp.091010.140711s.

@article{HANSEN2012834,
    author = "Gaston, D. and Guo, L. and Hansen, G. and Huang, H. and Johnson, R. and Knoll, D. and Newman, C. and Park, H.K. and Podgorney, R. and Tonks, M. and Williamson, R.",
    title = "Parallel Algorithms and Software for Nuclear, Energy, and Environmental Applications. {Part II: M}ultiphysics Software",
    journal = "Communications in Computational Physics",
    volume = "12",
    number = "3",
    comment = "INL/JOU-10-25162",
    year = "2012",
    pages = "834-865",
    publisher = "Idaho National Laboratory (INL)",
    doi = "10.4208/cicp.091010.140711s"
}

R.L. Williamson. Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior. Journal of Nuclear Materials, 415(1):74–83, 2011. doi:10.1016/j.jnucmat.2011.05.044.

@article{WILLIAMSON201174,
    author = "Williamson, R.L.",
    title = "Enhancing the {ABAQUS} thermomechanics code to simulate multipellet steady and transient {LWR} fuel rod behavior",
    journal = "Journal of Nuclear Materials",
    volume = "415",
    number = "1",
    pages = "74-83",
    year = "2011",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2011.05.044"
}

C. Newman, G. Hansen, and D. Gaston. Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in uo2 nuclear fuel rods. Journal of Nuclear Materials, 392(1):6–15, 2009. doi:10.1016/j.jnucmat.2009.03.035.

@article{NEWMAN20096,
    author = "Newman, C. and Hansen, G. and Gaston, D.",
    title = "Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods",
    journal = "Journal of Nuclear Materials",
    volume = "392",
    number = "1",
    pages = "6-15",
    year = "2009",
    issn = "0022-3115",
    doi = "10.1016/j.jnucmat.2009.03.035"
}

M. Tonks, D. Gaston, C. Permann, P. Millett, G. Hansen, and D. Wolf. A coupling methodology for mesoscale-informed nuclear fuel performance codes. Nuclear Engineering and Design, 240(10):2877–2883, 2010. 4th International Topical Meeting on High Temperature Reactor Technology (HTR 2008), with Regular Papers. doi:10.1016/j.nucengdes.2010.06.005.

@article{TONKS20102877,
    author = "Tonks, M. and Gaston, D. and Permann, C. and Millett, P. and Hansen, G. and Wolf, D.",
    title = "A coupling methodology for mesoscale-informed nuclear fuel performance codes",
    journal = "Nuclear Engineering and Design",
    volume = "240",
    number = "10",
    pages = "2877-2883",
    year = "2010",
    note = "4th International Topical Meeting on High Temperature Reactor Technology (HTR 2008), with Regular Papers",
    issn = "0029-5493",
    doi = "10.1016/j.nucengdes.2010.06.005"
}

Papers by the Bison Team