Journal Articles using BISON

Papers by the BISON Team

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. URL: http://www.sciencedirect.com/science/article/pii/S0022311518310298, doi:https://doi.org/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 = "https://doi.org/10.1016/j.jnucmat.2018.12.037",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311518310298"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0029549318310173, doi:https://doi.org/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 = "https://doi.org/10.1016/j.nucengdes.2018.12.005",
    url = "http://www.sciencedirect.com/science/article/pii/S0029549318310173",
    abstract = "In oxide nuclear fuel, the temperature gradient from the centerline to the radial edge of the pellet induces cracking due to thermal stress. We present a model that represents the effect of cracking as an isotropic softening of the material. The model considers a reduction of the elastic constants as a function of the number of cracks present in the fuel. This pragmatic approach aims to represent the average effect of cracking on the fuel stresses without attempting to explicitly describe the crack pattern or localization. Albeit simplistic, this approach has definite advantages in terms of computational expense and numerical convergence behavior for the mechanical analysis. It is also consistent with the uncertainties inherent in modeling the fuel cracking process, and suitable for engineering calculations aimed at representing the global fuel element behavior. The applied scaling of the elastic constants conserves the principal strain values and redistributes the principal stresses isotropically. Moreover, the model allows for the effect of an evolving number of cracks. In particular, an empirical correlation for the number of cracks as a function of the rod average linear heat rate is developed. Although the basic concept of the model was known, in this work we revisit and improve the original formulation, and implement the model in the BISON fuel performance code. Application in BISON is demonstrated through simulations of an idealized single fuel pellet irradiation and two integral fuel rod experiments. Results showcase the impact on calculated fuel stresses, the coupling to fuel creep, and the effect on cladding strains during pellet-cladding mechanical interaction."
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S002954931830102X, doi:https://doi.org/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 = "https://doi.org/10.1016/j.nucengdes.2018.07.015",
    url = "http://www.sciencedirect.com/science/article/pii/S002954931830102X"
}Copy

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. URL: https://www.sciencedirect.com/science/article/pii/S0306454918303037, doi:https://doi.org/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 = "https://doi.org/10.1016/j.anucene.2018.06.001",
    url = "https://www.sciencedirect.com/science/article/pii/S0306454918303037",
    keywords = "Accident tolerant fuel, Chromium, Silicon carbide, Cladding, Nuclear fuel, BISON"
}Copy

Stephen Novascone, Pavel Medvedev, John W. Peterson, Yongfeng Zhang, and Jason Hales. Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method. Journal of Nuclear Materials, 508:226 – 236, 2018. URL: http://www.sciencedirect.com/science/article/pii/S0022311518302861, doi:https://doi.org/10.1016/j.jnucmat.2018.05.041.

@article{NOVASCONE2018226,
    author = "Novascone, Stephen and Medvedev, Pavel and Peterson, John W. and Zhang, Yongfeng and Hales, Jason",
    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 = "https://doi.org/10.1016/j.jnucmat.2018.05.041",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311518302861",
    keywords = "Nuclear fuel, Porosity, Fast mixed oxide, Finite element method"
}Copy

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, 2018. URL: http://www.sciencedirect.com/science/article/pii/S0022311517315039, doi:https://doi.org/10.1016/j.jnucmat.2018.02.024.

@article{PIZZOCRI2018,
    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",
    issn = "0022-3115",
    doi = "https://doi.org/10.1016/j.jnucmat.2018.02.024",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311517315039",
    keywords = "Fission gas behaviour, Intra-granular behaviour, Oxide fuel, Gaseous swelling, Fuel performance codes"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0022311516312740, doi:https://doi.org/10.1016/j.jnucmat.2017.04.039.

@article{gamble2017,
    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",
    doi = "https://doi.org/10.1016/j.jnucmat.2017.04.039",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311516312740"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0029549316302187, doi:http://dx.doi.org/10.1016/j.nucengdes.2016.07.008.

@article{Spencer2016,
    author = "Spencer, B. W. and Williamson, R. L. and Stafford, D. S. and Novascone, S. R. and Hales, J. D. and Pastore, G.",
    title = "3{D} Modeling of Missing Pellet Surface Defects in {BWR} Fuel",
    journal = "Nuclear Engineering and Design",
    volume = "307",
    pages = "155--171",
    year = "2016",
    doi = "http://dx.doi.org/10.1016/j.nucengdes.2016.07.008",
    url = "http://www.sciencedirect.com/science/article/pii/S0029549316302187"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0029549316000789, doi:http://dx.doi.org/10.1016/j.nucengdes.2016.02.020.

@article{Williamson2016,
    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",
    doi = "http://dx.doi.org/10.1016/j.nucengdes.2016.02.020",
    url = "http://www.sciencedirect.com/science/article/pii/S0029549316000789"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0029549315002757, doi:http://dx.doi.org/10.1016/j.nucengdes.2015.07.005.

@article{Novascone2015,
    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 = "http://dx.doi.org/10.1016/j.nucengdes.2015.07.005",
    url = "http://www.sciencedirect.com/science/article/pii/S0029549315002757",
    abstract = "Many problems of interest, particularly in the nuclear engineering field, involve coupling between the thermal and mechanical response of an engineered system. The strength of the two-way feedback between the thermal and mechanical solution fields can vary significantly depending on the problem. Contact problems exhibit a particularly high degree of two-way feedback between those fields. This paper describes and demonstrates the application of a flexible simulation environment that permits the solution of coupled physics problems using either a tightly coupled approach or a loosely coupled approach. In the tight coupling approach, Newton iterations include the coupling effects between all physics, while in the loosely coupled approach, the individual physics models are solved independently, and fixed-point iterations are performed until the coupled system is converged. These approaches are applied to simple demonstration problems and to realistic nuclear engineering applications. The demonstration problems consist of single and multi-domain thermomechanics with and without thermal and mechanical contact. Simulations of a reactor pressure vessel under pressurized thermal shock conditions and a simulation of light water reactor fuel are also presented. Problems that include thermal and mechanical contact, such as the contact between the fuel and cladding in the fuel simulation, exhibit much stronger two-way feedback between the thermal and mechanical solutions, and as a result, are better solved using a tight coupling strategy."
}Copy

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, November 2015. URL: http://www.sciencedirect.com/science/article/pii/S0306454915003461, doi:http://dx.doi.org/10.1016/j.anucene.2015.06.032.

@article{Wu2015,
    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",
    month = "November",
    issn = "0306-4549",
    doi = "http://dx.doi.org/10.1016/j.anucene.2015.06.032",
    url = "http://www.sciencedirect.com/science/article/pii/S0306454915003461"
}Copy

D. S. Stafford. Multidimensional simulations of hydrides during fuel rod lifecycle. Journal of Nuclear Materials, 466(0):362–372, 2015. URL: http://www.sciencedirect.com/science/article/pii/S0022311515300623, doi:http://dx.doi.org/10.1016/j.jnucmat.2015.06.037.

@article{Stafford2015,
    author = "Stafford, D. S.",
    title = "Multidimensional simulations of hydrides during fuel rod lifecycle",
    journal = "Journal of Nuclear Materials",
    volume = "466",
    number = "0",
    pages = "362--372",
    year = "2015",
    issn = "0022-3115",
    doi = "http://dx.doi.org/10.1016/j.jnucmat.2015.06.037",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311515300623",
    abstract = "In light water reactor fuel rods, waterside corrosion of zirconium-alloy cladding introduces hydrogen into the cladding, where it is slightly soluble. When the solubility limit is reached, the hydrogen precipitates into crystals of zirconium hydride which decrease the ductility of the cladding and may lead to cladding failure during dry storage or transportation events. The distribution of the hydride phase and the orientation of the crystals depend on the history of the spatial temperature and stress profiles in the cladding. In this work, we have expanded the existing hydride modeling capability in the \{BISON\} fuel performance code with the goal of predicting both global and local effects on the radial, azimuthal and axial distribution of the hydride phase. We compare results from 1D simulations to published experimental data. We demonstrate the new capability by simulating in 2D a fuel rod throughout a lifecycle that includes irradiation, short-term storage in the spent fuel pool, drying, and interim storage in a dry cask. Using the 2D simulations, we present qualitative predictions of the effects of the inter-pellet gap and the drying conditions on the growth of a hydride rim."
}Copy

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"
}Copy

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, October 2014. URL: http://dx.doi.org/10.1016/j.anucene.2014.11.003, doi:10.1016/j.anucene.2014.11.003.

@Article{hales14multiphysics,
    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",
    year = "2014",
    volume = "84",
    month = "October",
    pages = "98--110",
    doi = "10.1016/j.anucene.2014.11.003",
    url = "http://dx.doi.org/10.1016/j.anucene.2014.11.003"
}Copy

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. URL: http://www.sciencedirect.com/science/article/pii/S0022311514006771, doi:http://dx.doi.org/10.1016/j.jnucmat.2014.09.077.

@article{pastore_et_al_2014,
    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{ U}ffelen, 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 = "http://dx.doi.org/10.1016/j.jnucmat.2014.09.077",
    url = "http://www.sciencedirect.com/science/article/pii/S0022311514006771",
    abstract = "Abstract The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the \{BISON\} fuel performance code with a recently implemented physics-based model for fission gas release and swelling. Through the integration of \{BISON\} with the \{DAKOTA\} software, a sensitivity analysis of the results to selected model parameters is carried out based on \{UO2\} single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information in the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior predictions with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, significantly higher deviations may be expected for values around 10\\% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes."
}Copy

Hai Huang, Benjamin Spencer, and Jason 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. URL: http://www.sciencedirect.com/science/article/pii/S0029549314004440, doi:http://dx.doi.org/10.1016/j.nucengdes.2014.05.049.

@article{Huang2014515,
    author = "Huang, Hai and Spencer, Benjamin and Hales, Jason",
    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",
    note = "",
    issn = "0029-5493",
    doi = "http://dx.doi.org/10.1016/j.nucengdes.2014.05.049",
    url = "http://www.sciencedirect.com/science/article/pii/S0029549314004440",
    abstract = "Abstract A discrete element method (DEM) representation of coupled solid mechanics, fracturing and heat conduction processes is developed and applied to explicitly simulate the random initiation and subsequent propagation of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The \{DEM\} model clearly predicts realistic early-life crack patterns including both radial and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations."
}Copy

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

@article{courty14,
    Author = "Courty, Olivier and Motta, Arthur T. and Hales, Jason D.",
    Journal = "Journal of Nuclear Materials",
    Title = "Modeling and simulation of hydrogen behavior in {Zircaloy-4} fuel cladding",
    Volume = "452",
    Pages = "311--320",
    Doi = "10.1016/j.jnucmat.2014.05.013",
    Url = "http://dx.doi.org/10.1016/j.jnucmat.2014.05.013",
    Year = "2014"
}Copy

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, September 2014. URL: http://dx.doi.org/10.1016/j.anucene.2014.03.027, doi:10.1016/j.anucene.2014.03.027.

@article{hales14verification,
    Author = "Hales, J. D. and Novascone, S. R. and Spencer, B. W. and Williamson, R. L. and Pastore, G. and Perez, D. M.",
    Journal = "Annals of Nuclear Energy",
    Title = "Verification of the {BISON} Fuel Performance Code",
    Volume = "71",
    Pages = "81--90",
    Doi = "10.1016/j.anucene.2014.03.027",
    Url = "http://dx.doi.org/10.1016/j.anucene.2014.03.027",
    Month = "September",
    Year = "2014"
}Copy

M. C. Teague, M. R. Tonks, S. R. Novascone, and S. R. Hayes. Microstructural modeling of thermal conductivity of high burnup mixed oxide fuel. Journal of Nuclear Materials, 444:161–169, 2014. URL: http://dx.doi.org/10.1016/j.jnucmat.2013.09.035, doi:10.1016/j.jnucmat.2013.09.035.

@article{teague14,
    Author = "Teague, M. C. and Tonks, M. R. and Novascone, S. R. and Hayes, S. R.",
    Journal = "Journal of Nuclear Materials",
    Volume = "444",
    Pages = "161--169",
    Title = "Microstructural modeling of thermal conductivity of high burnup mixed oxide fuel",
    Url = "http://dx.doi.org/10.1016/j.jnucmat.2013.09.035",
    Doi = "10.1016/j.jnucmat.2013.09.035",
    Year = "2014"
}Copy

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, 443:531–543, November 2013. URL: http://dx.doi.org/10.1016/j.jnucmat.2013.07.070, doi:10.1016/j.jnucmat.2013.07.070.

@article{hales13triso,
    Author = "Hales, J. D. and Williamson, R. L. and Novascone, S. R. and Perez, D. M. and Spencer, B. W. and Pastore, G.",
    Journal = "Journal of Nuclear Materials",
    Title = "Multidimensional multiphysics simulation of {TRISO} particle fuel",
    Volume = "443",
    Pages = "531--543",
    Month = "November",
    Year = "2013",
    Doi = "10.1016/j.jnucmat.2013.07.070",
    Url = "http://dx.doi.org/10.1016/j.jnucmat.2013.07.070"
}Copy

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, 440:193–200, 2013. URL: http://dx.doi.org/10.1016/j.jnucmat.2013.05.008, doi:10.1016/j.jnucmat.2013.05.008.

@article{tonks13thcon,
    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.",
    Journal = "Journal of Nuclear Materials",
    Title = "Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations",
    Pages = "193--200",
    Volume = "440",
    Doi = "10.1016/j.jnucmat.2013.05.008",
    Url = "http://dx.doi.org/10.1016/j.jnucmat.2013.05.008",
    Year = "2013"
}Copy

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, 423:149–163, 2012. URL: http://dx.doi.org/10.1016/j.jnucmat.2012.01.012, doi:10.1016/j.jnucmat.2012.01.012.

@article{Williamson2012,
    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.",
    Doi = "10.1016/j.jnucmat.2012.01.012",
    Issn = "0022-3115",
    Journal = "Journal of Nuclear Materials",
    Keywords = "PCMI",
    Pages = "149--163",
    Title = "Multidimensional Multiphysics Simulation of Nuclear Fuel Behavior",
    Volume = "423",
    Year = "2012",
    Url = "http://dx.doi.org/10.1016/j.jnucmat.2012.01.012"
}Copy

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. URL: http://dx.doi.org/10.3970/cmes.2012.084.123, doi:10.3970/cmes.2012.084.123.

@article{hales12,
    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",
    Url = "http://dx.doi.org/10.3970/cmes.2012.084.123",
    Year = "2012"
}Copy

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, 51:1–11, 2013. URL: http://dx.doi.org/10.1007/s00466-012-0741-7, doi:10.1007/s00466-012-0741-7.

@article{chockalingam2012crystal,
    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 = "1--11",
    year = "2013",
    volume = "51",
    publisher = "Springer",
    doi = "10.1007/s00466-012-0741-7",
    url = "http://dx.doi.org/10.1007/s00466-012-0741-7"
}Copy

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(INL/JOU-10-20006):807–833, 2012.

@article{hansen.ea10a,
    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: Multiphysics Algorithms",
    journal = "Communications in Computational Physics",
    volume = "12",
    number = "INL/JOU-10-20006",
    year = "2012",
    Pages = "807--833",
    publisher = "Idaho National Laboratory (INL)"
}Copy

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(INL/JOU-10-25162):834–865, 2012.

@article{hansen.ea10b,
    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: Multiphysics Software",
    journal = "Communications in Computational Physics",
    volume = "12",
    number = "INL/JOU-10-25162",
    year = "2012",
    Pages = "834--865",
    publisher = "Idaho National Laboratory (INL)"
}Copy

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

@article{williamson11,
    Author = "Williamson, R. L.",
    Doi = "10.1016/j.jnucmat.2011.05.044",
    Journal = "Journal of Nuclear Materials",
    Pages = "74",
    Title = "Enhancing the {ABAQUS} thermomechanics code to simulate multipellet steady and transient {LWR} fuel rod behavior",
    Volume = "415",
    Year = "2011",
    Bdsk-Url-1 = "http://dx.doi.org/10.1016/j.jnucmat.2011.05.044"
}Copy

C. Newman, G. Hansen, and D. Gaston. Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in $\mathrm UO_2$ nuclear fuel rods. Journal of Nuclear Materials, 392:6–15, 2009.

@article{thermooxy08,
    Author = "Newman, C. and Hansen, G. and Gaston, D.",
    Journal = "Journal of Nuclear Materials",
    Pages = "6--15",
    Title = "Three Dimensional Coupled Simulation of Thermomechanics, Heat, and Oxygen Diffusion in $\mathrm{UO}\_2$ Nuclear Fuel Rods",
    Volume = "392",
    Year = "2009",
    Bdsk-Url-1 = "http://dx.doi.org/10.1016/j.jnucmat.2009.03.035"
}Copy

Michael Tonks, Derek Gaston, Cody Permann, Paul Millett, Glen Hansen, and Dieter Wolf. A coupling methodology for mesoscale-informed nuclear fuel performance codes. Nuclear Engineering and Design, 240(10):2877–2883, 2010.

@article{tonks09a,
    Author = "Tonks, Michael and Gaston, Derek and Permann, Cody and Millett, Paul and Hansen, Glen and Wolf, Dieter",
    Journal = "Nuclear Engineering and Design",
    Number = "10",
    Pages = "2877--2883",
    Title = "A Coupling Methodology for Mesoscale-Informed Nuclear Fuel Performance Codes",
    Volume = "240",
    Year = "2010",
    Bdsk-Url-1 = "http://dx.doi.org/10.1016/j.nucengdes.2010.06.005."
}Copy

Papers by the BISON Team