Search Results - "Williamson, R.L."

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  1. 1

    Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling by Pastore, Giovanni, Swiler, L.P., Hales, J.D., Novascone, S.R., Perez, D.M., Spencer, B.W., Luzzi, L., Van Uffelen, P., Williamson, R.L.

    Published in Journal of nuclear materials (01-01-2015)
    “…The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel…”
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  2. 2

    Validating the BISON fuel performance code to integral LWR experiments by Williamson, R.L., Gamble, K.A., Perez, D.M., Novascone, S.R., Pastore, G., Gardner, R.J., Hales, J.D., Liu, W., Mai, A.

    Published in Nuclear engineering and design (01-05-2016)
    “…•The BISON multidimensional fuel performance code is being validated to integral LWR experiments.•Code and solution verification are necessary prerequisites to…”
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  3. 3

    Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS by Barani, T., Bruschi, E., Pizzocri, D., Pastore, G., Van Uffelen, P., Williamson, R.L., Luzzi, L.

    Published in Journal of nuclear materials (01-04-2017)
    “…The modelling of fission gas behaviour is a crucial aspect of nuclear fuel performance analysis in view of the related effects on the thermo-mechanical…”
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  4. 4

    3D modeling of missing pellet surface defects in BWR fuel by Spencer, B.W., Williamson, R.L., Stafford, D.S., Novascone, S.R., Hales, J.D., Pastore, G.

    Published in Nuclear engineering and design (01-10-2016)
    “…•A global/local analysis procedure for missing pellet surface defects is proposed.•This is applied to defective BWR fuel under blade withdrawal and high power…”
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  5. 5

    Multidimensional multiphysics simulation of nuclear fuel behavior by Williamson, R.L., Hales, J.D., Novascone, S.R., Tonks, M.R., Gaston, D.R., Permann, C.J., Andrs, D., Martineau, R.C.

    Published in Journal of nuclear materials (01-04-2012)
    “…Nuclear fuel operates in an environment that induces complex multiphysics phenomena, occurring over distances ranging from inter-atomic spacing to meters, and…”
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  6. 6

    Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments by Pastore, G., Williamson, R.L., Gardner, R.J., Novascone, S.R., Tompkins, J.B., Gamble, K.A., Hales, J.D.

    Published in Journal of nuclear materials (01-01-2021)
    “…BISON is a finite-element based, multidimensional fuel performance code developed at Idaho National Laboratory. In this paper, we present BISON modeling…”
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  7. 7

    Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior by Williamson, R.L.

    Published in Journal of nuclear materials (01-08-2011)
    “…► The ABAQUS thermomechanics code is enhanced to enable simulation of nuclear fuel behavior. ► Comparisons are made between discrete and smeared fuel pellet…”
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  8. 8
  9. 9

    Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments by Pastore, G., Gamble, K.A., Williamson, R.L., Novascone, S.R., Gardner, R.J., Hales, J.D.

    Published in Journal of nuclear materials (01-03-2021)
    “…In the first part of this work, we discussed BISON fuel performance code developments for Zircaloy cladding behavior under loss-of-coolant accident (LOCA)…”
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  10. 10

    Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x: Implications for nuclear fuel performance modeling by Andersson, D.A., Garcia, P., Liu, X.-Y., Pastore, G., Tonks, M., Millett, P., Dorado, B., Gaston, D.R., Andrs, D., Williamson, R.L., Martineau, R.C., Uberuaga, B.P., Stanek, C.R.

    Published in Journal of nuclear materials (01-08-2014)
    “…Based on density functional theory (DFT) and empirical potential calculations, the diffusivity of fission gas atoms (Xe) in UO2 nuclear fuel has been…”
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  11. 11

    Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code by Williamson, R. L., Capps, N. A., Liu, W., Rashid, Y. R., Wirth, B. D.

    Published in JOM (1989) (01-11-2016)
    “…Nuclear fuel operates in an extreme environment that induces complex multiphysics phenomena occurring over distances ranging from inter-atomic spacing to…”
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  12. 12

    Verification of the BISON fuel performance code by Hales, J.D., Novascone, S.R., Spencer, B.W., Williamson, R.L., Pastore, G., Perez, D.M.

    Published in Annals of nuclear energy (01-09-2014)
    “…•Reviews the accepted definitions of verification and validation.•Reviews verification papers from the literature.•Gives several example of verification tests…”
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  13. 13

    Multidimensional multiphysics simulation of TRISO particle fuel by Hales, J.D., Williamson, R.L., Novascone, S.R., Perez, D.M., Spencer, B.W., Pastore, G.

    Published in Journal of nuclear materials (01-11-2013)
    “…Multidimensional multiphysics analysis of TRISO-coated particle fuel using the BISON finite element nuclear fuels code is described. The governing equations…”
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  14. 14

    The US Department of Energy’s high temperature reactor research and development program – Progress as of 2019 by Gougar, H.D., Petti, D.A., Demkowicz, P.A., Windes, W.E., Strydom, G., Kinsey, J.C., Ortensi, J., Plummer, M., Skerjanc, W., Williamson, R.L., Wright, R.N., Li, D., Caponiti, A., Feltus, M.A., O'Connor, T.J.

    Published in Nuclear engineering and design (01-03-2020)
    “…•The High Temperature Gas-Cooled Reactor is a relatively mature technology; deployable within a decade.•US Department of Energy sponsorship of HTGR technology…”
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  15. 15

    Short-pulse microwave treatment of disseminated sulfide ores by Salsman, J.B., Williamson, R.L., Tolley, W.K., Rice, D.A.

    Published in Minerals engineering (1996)
    “…Theoretical and experimental analyses are used to study the feasibility of using short-pulse microwave energy as a pretreatment step in comminution. Ores of…”
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  16. 16

    Asymptotic expansion homogenization for multiscale nuclear fuel analysis by Hales, J.D., Tonks, M.R., Chockalingam, K., Perez, D.M., Novascone, S.R., Spencer, B.W., Williamson, R.L.

    Published in Computational materials science (01-03-2015)
    “…[Display omitted] •Review of AEH equations.•Calculation of correct solutions to standard problems.•Application of AEH to cladding and fuel.•Demonstration of…”
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  17. 17

    Evaluation of coupling approaches for thermomechanical simulations by Novascone, S.R., Spencer, B.W., Hales, J.D., Williamson, R.L.

    Published in Nuclear engineering and design (15-12-2015)
    “…•Use consistent convergence criteria when comparing coupling approaches.•Systems of equations with one-way feedback run faster with loose coupling.•Two-way…”
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  18. 18

    Advanced multiphysics coupling for LWR fuel performance analysis by Hales, J.D., Tonks, M.R., Gleicher, F.N., Spencer, B.W., Novascone, S.R., Williamson, R.L., Pastore, G., Perez, D.M.

    Published in Annals of nuclear energy (01-10-2015)
    “…•Overviews the BISON nuclear fuel performance analysis code.•Discusses loose and tight coupling approaches applied to thermomechanics.•Outlines coupling to the…”
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  19. 19

    Three-dimensional simulation of plasma spray: effects of carrier gas flow and particle injection on plasma jet and entrained particle behavior by Xiong, Hong-Bing, Zheng, Li-Li, Sampath, Sanjay, Williamson, Richard L., Fincke, Jim R.

    “…As important phenomena in plasma spray, the plasma jet perturbation by the carrier gas flow and particles loading, and their effects on particle behavior are…”
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  20. 20

    Entrainment in high-velocity, high-temperature plasma jets. Part I: experimental results by Fincke, J.R., Crawford, D.M., Snyder, S.C., Swank, W.D., Haggard, D.C., Williamson, R.L.

    “…The development of a high-velocity, high-temperature argon plasma jet issuing into air has been investigated. In particular the entrainment of the surrounding…”
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