Search Results - "Hales, J.D."

An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions by Gamble, K.A., Barani, T., Pizzocri, D., Hales, J.D., Terrani, K.A., Pastore, G.

“…Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel cladding for increased accident tolerance. An analysis of the response of…”
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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.

“…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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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.

“…•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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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.

“…•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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Analysis of buffer-IPyC separation in TRISO fuel particles by Krajewska, Z.M., Hales, J.D., Jiang, W.

“…During High Temperature Gas-cooled Reactor (HTGR) operation, and due to the neutron irradiation in the reactor core, damage of the nuclear fuel coating layers…”
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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.

“…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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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.

“…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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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions by Barani, T., Pastore, G., Pizzocri, D., Andersson, D.A., Matthews, C., Alfonsi, A., Gamble, K.A., Van Uffelen, P., Luzzi, L., Hales, J.D.

“…In this work, we present a model of fission gas behavior in U3Si2 under light water reactor (LWR) conditions for application in engineering fuel performance…”
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Mechanistic verification of empirical UO2 fuel fracture models by Gamble, K.A., Knight, T.W., Roberts, E., Hales, J.D., Spencer, B.W.

“…•The tensile strength of UO2 is the most sensitive material property determining crack formation.•Uniform and volume-weighted Weibull approaches to strength…”
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Atomistic and cluster dynamics modeling of fission gas (Xe) diffusivity in TRISO fuel kernels by Liu, X.-Y., Matthews, C., Jiang, W., Cooper, M.W.D., Hales, J.D., Andersson, D.A.

“…TRISO fuel particles are candidates for use in next generation reactors including gas reactors, fluoride salt-cooled high temperature reactors, and…”
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Isotropic softening model for fuel cracking in BISON by Barani, T., Pizzocri, D., Pastore, G., Luzzi, L., Hales, J.D.

“…•Model to represent the effect of cracking as an isotropic softening of the material.•Computationally efficient means to account for fuel cracking in…”
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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.

“…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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A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools by Pizzocri, D., Pastore, G., Barani, T., Magni, A., Luzzi, L., Van Uffelen, P., Pitts, S.A., Alfonsi, A., Hales, J.D.

“…The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear…”
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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.

“…•Reviews the accepted definitions of verification and validation.•Reviews verification papers from the literature.•Gives several example of verification tests…”
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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.

“…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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A layered 2D computational framework: Theory and applications to nuclear fuel behavior by Gamble, K.A., Spencer, B.W., Hales, J.D., Knight, T.W., Roberts, E.

“…Nuclear fuel performance computer codes have been developed over the last 50 years to analyze fuel behavior under various operating conditions. Traditionally,…”
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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.

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

“…•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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Crystal plasticity with Jacobian-Free Newton–Krylov by Chockalingam, K., Tonks, M. R., Hales, J. D., Gaston, D. R., Millett, P. C., Zhang, Liangzhe

“…The objective of this work is to study potential benefits of solving crystal plasticity finite element method (CPFEM) implicit simulations using the…”
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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.

“…•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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