Skip Ribbon Commands
Skip to main content

Team Members

​​​​​​​​​​​​​​​​​​​​​​​

 

 

Richard Williamson, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=54Richard Williamson, Ph.D.Richard Williamson created the Bison development team within the Fuel Modeling and Simulation Department at Idaho National Laboratory. He has 40+ years experience in computational methods research and model development. His current research relates to developing models to simulate nuclear fuel behavior with specific emphasis on complex multiphysics and multidimensional phenomena.  Dr. Williamson has over 50 peer-reviewed journal articles and many hundreds of citations to his work. He received his Ph.D. in Mechanical Engineering from the University of Idaho in 1989.https://bios.inl.gov/BioPhotos/Richard%20Williamson.JPGMechanical EngineerWilliamsonRichard
Jason Hales, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=49Jason Hales, Ph.D.Jason Hales is a computational scientist specializing in parallel, nonlinear, fully-coupled multi-physics software. His technical skills include numerical methods, high performance computing, non-linear solid mechanics, material model development, finite element contact, and multi-physics coupling. Dr. Hales joined INL in 2010 with a principal focus on non-linear solid mechanics capability development. He is the primary author of Bison, INL’s nuclear fuel performance application. Dr. Hales now manages INL’s Fuel Modeling and Simulation Department, which develops a set of multi-physics applications in support of several DOE-NE programs. Before joining INL he spent nine years at Sandia National Laboratories where he worked on the solid mechanics applications in SIERRA. Dr. Hales holds B.S. and M.S. degrees in civil engineering from Brigham Young University and a Ph.D. in civil engineering from the University of Illinois at Urbana-Champaign.<div class="ExternalClass5695DF14FF814B9CB2690CB233E7DFC5"><p>​Ph.D., Civil Engineering - University of Illinois, Urbana-Champaign</p><p>M.S., CIvil and Environmental Engineering - Brigham Young University</p><p>B.S., Civil and Environmental Engineering - Brigham Young University</p></div><div class="ExternalClassAA81C242E6FC4628A67F8F39770000B2"><p>T. Barani, G. Pastore, D. Pizzocri, D. Andersson, C. Matthews, A. Alfonsi, K. Gamble, P. V. Uffelen, L. Luzzi, and J. Hales, “Multiscale modeling of fission gas behavior in u3si2 under lwr conditions,” Journal of Nuclear Materials, vol. 522, pp. 97 – 110, 2019. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311519301151">http://www.sciencedirect.com/science/article/pii/S0022311519301151</a><br></p><p>P. V. Uffelen, J. Hales, W. Li, G. Rossiter, and R. Williamson, “A review of fuel performance modelling,” Journal of Nuclear Materials, vol. 516, pp. 373 – 412, 2019. Online at <a href="http://www.sciencedirect.com/%20science/article/pii/S0022311518310298">http://www.sciencedirect.com/ science/article/pii/S0022311518310298</a><br></p><p>T. Barani, D. Pizzocri, G. Pastore, L. Luzzi, and J. Hales, “Isotropic softening model for fuel cracking in BISON,” Nuclear Engineering and Design, vol. 342, pp. 257 – 263, 2019. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0029549318310173">http://www.sciencedirect.com/science/article/pii/S0029549318310173</a><br></p><p>Y. Che, G. Pastore, J. Hales, and K. Shirvan, “Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code,” Nuclear Engineering and Design, vol. 337, pp. 271 – 278, 2018. Online at <a href="http://www.sciencedirect.com/science/article/pii/S002954931830102X">http://www.sciencedirect.com/science/article/pii/S002954931830102X</a><br></p><p>M.Wagih,B.Spencer,J.Hales,andK.Shirvan,“Fuelperformanceofchromium-coatedzirconiumalloy and silicon carbide accident tolerant fuel claddings,” Annals of Nuclear Energy, vol. 120, pp. 304 – 318, 2018. Online at <a href="https://www.sciencedirect.com/science/article/pii/S0306454918303037">https://www.sciencedirect.com/science/article/pii/S0306454918303037</a><br></p><div class="ExternalClassC0C7B49022524396A6349709E02B7AD1"><p>S.Novascone,P.Medvedev,J.W.Peterson,Y.Zhang,andJ.Hales,“ModelingporositymigrationinLWR and fast reactor MOX fuel using the finite element method,” Journal of Nuclear Materials, vol. 508, pp. 226 – 236, 2018. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311518302861">http://www.sciencedirect.com/science/article/pii/S0022311518302861</a><br></p><p><span aria-hidden="true"></span>​D. Pizzocri, G. Pastore, T. Barani, A. Magni, L. Luzzi, P. V. Uffelen, S. Pitts, A. Alfonsi, and J. Hales, “A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools,” Journal of Nuclear Materials, 2018. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311517315039"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0022311517315039</font></span></a><br></p><p>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, vol. 491, pp. 55–66, 2017. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311516312740"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0022311516312740</font></span></a><br></p><p>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, vol. 307, pp. 155–171,<br>2016. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0029549316302187"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0029549316302187</font></span></a><br></p><p>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, vol. 301, pp. 232–244, 2016. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0029549316000789"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0029549316000789</font></span></a><br></p><p>X.-M. Bai, M. R. Tonks, Y. Zhang, and J. D. Hales, “Multiscale modeling of thermal conductivity of high burnup structures in UO2 fuels,” Journal of Nuclear Materials, vol. 470, pp. 208–215, 2016. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311515303974"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0022311515303974</font></span></a><br></p><p>S. R. Novascone, B. W. Spencer, J. D. Hales, and R. L. Williamson, “Evaluation of coupling approaches for thermomechanical simulations,” Nuclear Engineering and Design, vol. 295, pp. 910–921, 2015. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0029549315002757"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0029549315002757</font></span></a><br></p><p>X. Wu, T. Kozlowski, and J. D. Hales, “Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions,” Annals of Nuclear Energy, vol. 85, pp. 763–775, November 2015. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0306454915003461"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0306454915003461</font></span></a></p><p> 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, vol. 99, pp. 290–297, March 2015. Online at <a href="http://dx.doi.org/10.1016/j.commatsci.2014.12.039"><font color="#0066cc">http://dx.doi.org/10.1016/j.commatsci.2014.12.039</font></a></p><p>G. 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<br>engineering-scale fuel modeling,” Journal of Nuclear Materials, vol. 456, pp. 398–408, 2015. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0022311514006771"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0022311514006771</font></span></a><br></p><p>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,” Ann. Nuclear Energy, vol. 84, pp. 98–110, October 2014. Online at <a href="http://dx.doi.org/10.1016/j.anucene.2014.11.003"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.1016/j.anucene.2014.11.003</font></span></a><br></p><p>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, vol. 278, pp. 515 – 528, 2014. Online at <a href="http://www.sciencedirect.com/science/article/pii/S0029549314004440"><span style="text-decoration:underline;"><font color="#0066cc">http://www.sciencedirect.com/science/article/pii/S0029549314004440</font></span></a></p><p> O. Courty, A. T. Motta, and J. D. Hales, “Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding,” J. Nucl. Mater., vol. 452, pp. 311–320, 2014. Online at <a href="http://dx.doi.org/10.1016/j.jnucmat"><font color="#0066cc"></font></a><a href="http://dx.doi.org/10.1016/j.jnucmat.2014.05.013">http://dx.doi.org/10.1016/j.jnucmat.2014.05.013</a><br></p><p>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,” Ann. Nuclear Energy, vol. 71, pp. 81–90, September 2014. Online at <a href="http://dx.doi.org/10.1016/j.anucene.2014.03.027"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.1016/j.anucene.2014.03.027</font></span></a><br></p><p>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,” J. Nucl. Mater., vol. 443, pp.531–543, November 2013. Online at <a href="http://dx.doi.org/10.1016/j.jnucmat.2013.07.070"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.1016/j.jnucmat.2013.07.070</font></span></a><br></p><p>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, vol. 51, pp. 1–11, 2013. Online at<br><a href="http://dx.doi.org/10.1007/s00466-012-0741-7"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.1007/s00466-012-0741-7</font></span></a><br></p><p>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,” J. Nucl. Mater., vol. 423, pp. 149–163, 2012. Online at <a href="http://dx.doi.org/10.1016/j.jnucmat.2012.01.012"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.1016/j.jnucmat.2012.01.012</font></span></a></p><p>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,” CMES: Comput. Model. Eng. Sci., vol. 84, no. 2, pp. 123–154, 2012. Online at <a href="http://dx.doi.org/10.3970/cmes.2012.084.123"><span style="text-decoration:underline;"><font color="#0066cc">http://dx.doi.org/10.3970/cmes.2012.084.123</font></span></a><span aria-hidden="true"></span></p></div></div>https://bios.inl.gov/BioPhotos/JasonHales.jpgDepartment ManagerHalesJason
Stephen Novascone, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=53Stephen Novascone, Ph.D.Stephen Novascone is a computational scientist at Idaho National Laboratory (INL), with a background/education in mechanical engineering. After finishing his Master of Science degree in Mechanical Engineering at Utah State University in 1998, he had a brief stint at Thiokol, analyzing rocket motors. Raised in Idaho and wanting to return, he seized an opportunity to work at the Idaho National Engineering and Environmental Laboratory in 1999. Since then, he has spent most of his 20+ year career at INL working on a variety of engineering projects, including research on geo-material sensors, which was the topic of his dissertation at the University of Idaho (Ph.D. 2003). Since 2010, he has worked as a developer of Bison, INL’s state-of-the-art nuclear fuel performance code. His role on the Bison team is to develop light water reactor, fast mixed oxide and metallic fuel simulation capability and evaluate the code against experimental measurements. While working on Bison, Stephen has authored/co-authored many peer-reviewed archival journal articles and delivered numerous presentations at national and international forums. According to Google Scholar, these publications have a citation count of > 800. Other notable achievements include patents for geo-material sensors and material testing apparatus for armor systems.https://bios.inl.gov/BioPhotos/Stephen%20Novascone.JPGMechanical EngineerNovasconeStephen
Giovanni Pastore, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=52Giovanni Pastore, Ph.D.Giovanni Pastore, Ph.D., is a research and development scientist at Idaho National Laboratory, where he leads the developers team for the nuclear fuel analysis code BISON. Dr. Pastore earned his master’s degree in Nuclear Engineering (2008) and Ph.D. cum laude (2012) from the Politecnico di Milano (Italy). Besides INL, he has worked at the European Commission (JRC-ITU Karlsruhe, Germany), the Halden Reactor Project (Norway) and the Massachusetts Institute of Technology (MIT). His research focuses mainly on software development for engineering nuclear fuel performance analysis and on advanced modeling of fission gas behavior.<div class="ExternalClass1940F139D68E4513981D4CEFBF5605DE"><p>​​Ph.D., Radiation Science and Technology - Politecnico di Milano</p><p>M.S., Nuclear Engineering - Politecnico di Milano</p><p>B.S., Physics Engineering - Politecnico di Milano<br></p></div><div class="ExternalClass3C453EF4A41F463D808A9ABD1E19B7C5"><p>​​M. Tonks, D. Andersson, R. Devanathan, R. Dubourg, A. El-Azab, M. Freyss, F. Iglesias, K. Kulacsy, G. Pastore, S.R. Phillpot , M. Welland, Unit mechanisms of fission gas release: Current understanding and future needs, Journal of Nuclear Materials, vol. 504, pp. 300-317, 2018.</p><p><br>D. Pizzocri, G. Pastore, T. Barani, A. Magni, L. Luzzi, P. Van Uffelen, S.A. Pitts, A. Alfonsi, J.D. Hales, A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, Journal of Nuclear Materials, vol. 502, pp. 323-330, 2018.</p><p><br>L. Luzzi, L. Cognini, D. Pizzocri, T. Barani, G. Pastore, A. Schubert, T. Wiss, P. Van Uffelen, Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, Nuclear Engineering and Design, vol. 330, 265-271, 2018.</p><p><br>K.A. Gamble, T. Barani, D. Pizzocri, J.D. Hales, K.A. Terrani, G. Pastore, An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions, Journal of Nuclear Materials, vol. 491, pp. 55-66, 2017.</p><p><br>D. Pizzocri, F. Cappia, L. Luzzi, G. Pastore, V.V. Rondinella, P. Van Uffelen, A semi-empirical model for the formation and depletion of the high burnup structure in UO2, Journal of Nuclear Materials, vol. 487, pp. 23-29, 2017.</p><p><br>T. Barani, E. Bruschi, D. Pizzocri, G. Pastore, P. Van Uffelen, R.L. Williamson, L. Luzzi, Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, Journal of Nuclear Materials, vol. 486, pp. 96-110, 2017.</p><p><br>B.W. Spencer, R.L. Williamson, D.S. Stafford, S.R. Novascone, J.D. Hales, G. Pastore, 3D modeling of missing pellet surface defects in BWR fuel, Nuclear Engineering and Design, vol. 307, pp. 155-171, 2016.</p><p><br>D. Pizzocri, C. Rabiti, L. Luzzi, T. Barani, P. Van Uffelen, G. Pastore, PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release, Journal of Nuclear Materials, vol. 478, pp. 333-342, 2016.</p><p><br>R.L. Williamson, K.A. Gamble, D.M. Perez, S.R. Novascone, G. Pastore, R.J. Gardner, J.D. Hales, W. Liu, A. Mai, Validating the BISON fuel performance code to integral LWR experiments, Nuclear Engineering and Design, vol. 301, pp. 232-244, 2016.</p><p><br>M.R. Tonks, X.-Y. Liu, D. Andersson, D. Perez, A. Chernatynskiy, G. Pastore, C.R. Stanek, R. Williamson, Development of a multiscale thermal conductivity model for fission gas in UO2, Journal of Nuclear Materials, vol. 469, pp. 89-98, 2016.</p><p><br>G. Pastore, L.P. Swiler, J.D. Hales, S.R. Novascone, D.M. Perez, B.W. Spencer, L. Luzzi, P. Van Uffelen, R.L. Williamson, Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling, Journal of Nuclear Materials, vol. 456, pp. 398-408, 2015.</p><p><br>J.D. Hales, M.R. Tonks, F.N. Gleicher, B.W. Spencer, S.R. Novascone, R.L. Williamson, G. Pastore, D.M. Perez, Advanced multiphysics coupling for LWR fuel performance analysis, Annals of Nuclear Energy, vol. 84, pp. 98-110, 2015.</p><p><br>P. Chakraborty, M.R. Tonks, G. Pastore, Modeling the influence of bubble pressure on grain boundary separation and fission gas release, Journal of Nuclear Materials, vol. 452, pp. 95-101, 2014.</p><p><br>D.A. Andersson, P. Garcia, X.-Y. Liu, G. Pastore, M.R. Tonks, P.C. Millett, B. Dorado, D.R. Gaston, D. Andrs, R.L. Williamson, R.C. Martineau, B.P. Uberuaga, C.R. Stanek, Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x: Implications for nuclear fuel performance modeling, Journal of Nuclear Materials, vol. 451, pp. 225-242, 2014.</p><p><br>J.D. Hales, S.R. Novascone, B.W. Spencer, R.L. Williamson, G. Pastore, D.M. Perez, Verification of the BISON fuel performance code, Annals of Nuclear Energy, vol. 71, pp. 81-90, 2014.</p><p><br>J.D. Hales, R.L. Williamson, S.R. Novascone, D.M. Perez, B.W. Spencer, G. Pastore, Multidimensional multiphysics simulation of TRISO particle fuel, Journal of Nuclear Materials, vol. 443, pp. 531-543, 2013.</p><p><br>G. Pastore, L. Luzzi, V. Di Marcello, P. Van Uffelen, Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis, Nuclear Engineering and Design, vol. 256, pp. 75-86, 2013.</p><p><br>P. Van Uffelen, G. Pastore, V. Di Marcello, L. Luzzi, Multiscale modelling for the fission gas behaviour in the TRANSURANUS code, Nuclear Engineering and Technology, vol. 43, no. 6, pp. 477-488, 2011.</p></div>https://bios.inl.gov/BioPhotos/Giovanni%20Pastore.JPGResearch and Development ScientistPastoreGiovanni
Benjamin Spencer, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=50Benjamin Spencer, Ph.D.Benjamin Spencer brings his computational solid mechanics expertise to the BISON development effort.  He has broad experience developing and applying computational methods for fracture, contact, constitutive modeling, and structural dynamics in massively parallel computing environments.  Prior to coming to INL in 2011, he worked at Sandia National Laboratories, where he developed implicit and explicit solid mechanics codes and simulated nuclear safety-related structures subjected to a variety of natural and man-made insults.  He received his Ph.D. in Civil Engineering from the University of Colorado at Boulder in 2002.<div class="ExternalClass42C7E998BE50419D9487CE4697DBDAC1"><p>​Ph.D., Civil Engineering - University of Colorado, Boulder</p><p>M.S., Civil Engineering - University of Colorado, Boulder</p><p>B.S., Civil Engineering - BrighamYoung University</p></div><div class="ExternalClassAFCC173A37424B8A9D7C412E6ECC5776"><p>​Y. Hu, H. Chen, B.W. Spencer, and E. Madenci, “Thermomechanical Peridynamic Analysis with Irregular Non-Uniform Domain Discretization”, Engineering Fracture Mechanics Feb. 2018.</p><p> </p><p>Z. Zhang, W. Jiang, J. E. Dolbow, and B.W. Spencer, “A modified moment-fitted integration scheme for X-FEM applications with history-dependent material data”, Computational Mechanics Jan. 2018.</p><p> </p><p>X.-M. Bai, H. Ke, Y. Zhang, and B.W. Spencer, “Modeling copper precipitation hardening and embrittlement in a dilute Fe-0.3at.%Cu alloy under neutron irradiation”, Journal of Nuclear Materials, vol. 495, pp. 442–454, Nov. 2017.</p><p><br>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, vol. 307, pp. 155–171, Oct. 2016.</p><p><br>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, vol. 84, pp. 98–110, Oct. 2015.</p><p><br>S. R. Novascone, B.W. Spencer, J.D. Hales, and R. L. Williamson, “Evaluation of coupling approaches for thermomechanical simulations”, Nuclear Engineering and Design, vol. 295, pp. 910–921, Aug. 2015.</p><p><br>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, vol. 99, pp. 290–297, Mar. 2015.</p><p><br>G. 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, vol. 456, pp. 398–408, Jan. 2015.</p><p> </p><p>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, vol. 278, pp. 515–528, Oct. 2014.</p><p> </p><p>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, vol. 71, pp. 81–90, Sept. 2014.</p><p> </p><p>G. J. de Fr´ıas, W. Aquino, K. H. Pierson, M.W. Heinstein, and B.W. Spencer, “A multiscale mass scaling approach for explicit time integration using proper orthogonal decomposition”, International Journal for Numerical Methods in Engineering, vol. 97, no. 11, pp. 799–818, Mar. 2014.</p><p> </p><p>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, vol. 443, pp. 531–543, 2013.</p><p> </p><p>J. P. Petti, B.W. Spencer, and H. L. Graves, “Risk-informed assessment of degraded containment vessels”, Nuclear Engineering and Design, vol. 238, no. 8, pp. 2038–2047, Aug. 2008.</p><p> </p><p>B.W. Spencer and P.B. Shing, “Rigid-plastic interface for an embedded crack”, International Journal For Numerical Methods In Engineering, vol. 56, pp. 2163–2182, 2003.</p></div>https://bios.inl.gov/BioPhotos/Benjamin%20Spencer.JPGTechnical StaffSpencerBenjamin
Kyle Gamblehttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=56Kyle GambleKyle Gamble is a computational mathematician/physicist in the Fuel Modeling and Simulation Department as a member of the BISON team. He started at INL in June 2014. Mr. Gamble obtained a B.Sc. in Engineering Physics from Queen's University in Kingston, Ontario, Canada (2012) and a M.A.Sc. in Nuclear Engineering from the Royal Military College of Canada (2014). His Master's research was in collaboration with Atomic Energy of Canada Limited Chalk River Laboratories examining the capabilities of the MOOSE/BISON framework at modeling thermally and mechanically induced deformations of CANada Deuterium Uranium (CANDU) reactor fuel elements in three dimensions. Mr. Gamble's research interests include finite element contact, fuel performance, modeling and mutliphysics. <div class="ExternalClass80E10A28E18547888CBDFE9983951C61"><p>​M.S., Chemistry and Chemical Engineering - Royal Military College of Canada</p><p>B.S., Engineering Physics, Mechanical Engineering Option - Queen's University, Canada</p></div><div class="ExternalClass70AAEAA7984A43CDB463FE74B9BA8EE6"><p>​Professional Engineers of Ontario</p><p>Canadian Nuclear Society</p><p>American Nuclear Society</p></div><div class="ExternalClassBC2A1FF8AA7E4E4F95023CCFDC82C8F1"><p><strong>​Refereed Journal Papers</strong><br>S. Stimpson, J. Powers, K. Clarno, R. Pawlowski, R. Gardner, S. Novascone, K. Gamble, R. Williamson, “Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1-3,” Journal of Nuclear Engineering and Design, 327 (2018), p. 172-186.</p><p><br>Y. Miao, K. A. Gamble, D. Andersson, Z-G Mei, A. M. Yacout, “Rate theory scenarios study on fission gas behavior of U3Si2 under LOCA conditions in LWRs,” Journal of Nuclear Engineering and Design, 326 (2018), p. 371-282.</p><p><br>Y. Miao, K. A. Gamble, D. Andersson, B. Ye, Z-G Mei, G. Hofman, A. M. Yacout, “Gaseous Swelling of U3Si2 during Steady-State LWR Operation: a Rate Theory Investigation,” Journal of Nuclear Engineering and Design, 322 (2017), p. 336-344.</p><p><br>K. A. Gamble, T. Barani, D. Pizzocri, J. D. Hales, K. A. Terrani, G. Pastore, “An investigation of FeCrAl cladding behaviour under normal operating and loss of coolant conditions,” Journal of Nuclear Materials, 491 (2017), p. 55-66.</p><p><br>R. L. Williamson, K. A. Gamble, D. M. Perez, S. R. Novascone, G. Pastore, R. J. Gardner, J. D. Hales, W. Liu, A. Mai, “Validating the BISON fuel performance code to integral LWR experiments,” Journal of Nuclear Engineering and Design, 301 (2016), p. 232-244.</p><p><br>K. A. Gamble, A. F. Williams, P. K. Chan, D. Wowk, “A feasibility study on the use of the MOOSE computational framework to simulate three-dimensional deformation of CANDU reactor fuel elements,” Journal of Nuclear Engineering and Design, 293 (2015), p. 385-394.</p><p><br>D. Wowk, K. Gamble, R. Underhill, "Influence of p-method finite element parameters on predictions of crack front geometry," Journal of Finite Element in Analysis and Design, 73 (2013),<br>p. 1-10.</p><p><br><strong>Conference Proceedings</strong><br>K. A. Gamble, J. D. Hales, G. Pastore, T. Barani, D. Pizzocri, K. A. Terrani, “Fuel Performance Modeling of FeCrAl Cladding Failure during Loss of Coolant Conditions,” Proceedings of the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea<br>(September 2017).</p><p><br>K. A. Gamble, J. D. Hales, “Preliminary Modeling of Accident Tolerant Fuel Concepts under Accident Conditions, Proceedings of TopFuel 2016, Boise, USA (September 2016).</p><p><br>K. A. Gamble, L. P. Swiler, “Uncertainty Quantification and Sensitivity Analysis Applications to Fuel Performance Modeling,” Proceedings of TopFuel 2016, Boise, USA (September 2016).</p><p><br>K. A. Gamble, J. D. Hales, "Investigating Accident Tolerant Fuel Concepts using the BISON Fuel Performance Code," Proceedings of the Nuclear Fuels and Structural Materials Embedded Topical – ANS Annual Meeting, New Orleans, LA, USA (June 2016).</p><p><br>J. D. Hales, K. A. Gamble, "Preliminary evaluation of FeCrAl cladding and U-Si fuel for accident tolerant fuel concepts," Proceedings of TopFuel 2015, Zurich, Switzerland (September 2015).</p><p><br>K. A. Gamble, "Overview of the BISON Fuel Performance Code," Proceedings of the ANS<br>Annual Meeting, San Antonio, TX, USA (June 2015).</p><p><br>K. A. Gamble, A.F. Williams, P.K. Chan, "Development of a Three-Dimensional Thermo-Mechanical Deformation Model of a Horizontal Nuclear Fuel Element," Proceedings of the 19th Pacific Basin Nuclear Conference, Vancouver, BC, Canada (August 2014).</p><p><br>K. Gamble, A.F. Williams, P.K. Chan, "A Three-Dimensional Analysis of the Stresses and Strains at the Pellet Ridges in a Horizontal Nuclear Fuel Element," Proceedings of the 22nd International Conference on Nuclear Engineering, Prague, Czech Republic (July 2014).</p><p><br>K. Gamble, A.F. Williams, P.K. Chan, "Feasibility Study of Modeling a CANDU Fuel Element using a Multiphysics Object-Oriented Simulation Environment," Proceedings of the 12th International Conference on CANDU Fuel, Kingston, ON, Canada (September 2013).</p><p><br>K. Gamble, A.F. Williams, P.K. Chan, "Advanced Finite Element Modeling of a Horizontal Nuclear Fuel Element using a Multiphysics Object-Oriented Simulation Environment," 37th Annual CNS/CNA Student Conference, Toronto, ON, Canada (June 2013).</p><p><strong></strong> </p><p><strong>Technical Industry Documents</strong><br>K. A. Gamble, J. D. Hales, G. Pastore, T. Barani, D. Pizzocri, “Behavior of U3Si2 Fuel and FeCrAl Cladding under Normal Operating and Accident Reactor Conditions, Technical Report, Idaho National Laboratory, INL/EXT-16-40059 (September 2016).</p><p><br>J. D. Hales, R. L. Williamson, S. R. Novascone, G. Pastore, B. W. Spencer, D. S. Stafford, K. A. Gamble, D. M. Perez, W. Liu, "BISON Theory Manual: The Equations Behind Nuclear Fuel Analysis, BISON Release 1.2," Technical Report, Idaho National Laboratory, INL/MIS-13-29930 Rev. 3 (September 2015).</p><p><br>J. D. Hales, K. A. Gamble, B. W. Spencer, S. R. Novascone, G. Pastore, W. Liu, D. S. Stafford, R. L. Williamson, D. M. Perez, R. J. Gardner, "BISON Users Manual, BISON Release 1.2," Technical Report, Idaho National Laboratory, INL/MIS-13-30307 Rev. 3<br>(September 2015).</p><p><br>K. A. Gamble, J. D. Hales, J. Yu, Y. Zhang, X. Bai, D. Andersson, A. Patra, W. Wen, C. Tomé, M. Baskes, E. Martinez, C. R. Stanek, Y. Miao, B. Ye, G. L. Hofman, A. M. Yacout, W. Liu, "Multiscale Multiphysics Developments for Accident Tolerant Fuel Concepts,"<br>Technical Report, Idaho National Laboratory, INL/EXT-15-36761 (September 2015).</p><p><br>K. Gamble, R. Williamson, D. Schwen, Y. Zhang, S. Novascone, P. Medvedev, "BISON and MARMOT Development for Modeling Fast Reactor Fuel Performance," Technical Report, Idaho National Laboratory, INL/EXT-15-36440 (September 2015).</p><p><br>M.H.A. Piro, J.J. Bashcuk, K. Gamble, B.W. Leitch, A.F. Williams, "Multi-Physics Software Comparison Between ANSYS and MOOSE/BISON/MARMOT," AECL Memo, Chalk River, ON, Canada, F&FCSB-13-060 (December 2013).</p></div>https://bios.inl.gov/BioPhotos/Kyle%20Gamble.JPGComputational Mathematician/PhysicistGambleKyle
Russell Gardnerhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=55Russell GardnerRussell Gardner received his Bachelor of Science Degree in Nuclear Engineering from Oregon State University in 2010. He started working at INL as an intern in 2009 and became a full-time employee July 2010 as an Experiment Power Reactor Operator at INL’s Advanced Test Reactor (ATR). Mr. Gardner spent 4 years at the ATR in nuclear operations before transferring to the fuel modeling and simulation department in early 2014. While originally brought in to the Bison team to help with the code assessment effort, his responsibilities expanded to tasks such as maintenance of the assessment bank and the associated nightly testing, working with the Japan Atomic Energy Agency (JAEA) on Mixed Oxide (MOX) fuel collaborations, training and general user support and working as a Bison point of contact for the Consortium for Advanced Simulation of Light Water Reactors (CASL) program.<div class="ExternalClassB3501FBCD3E04B53BECC2FD18229675D"><p>​B.S., Nuclear Engineering - Oregon State University</p></div>https://bios.inl.gov/BioPhotos/Russell%20Gardner.JPGNuclear EngineerGardnerRussell
Al Casagranda, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=377Al Casagranda, Ph.D.Al Casagranda is a computational scientist in the Fuel Modeling and Simulation Department at INL. He has degrees in Nuclear Engineering from Purdue University (B.S. – 1986, M.S. – 1988) and Materials Science from the University of California at Santa Barbara (Ph.D. – 1993). He has used and developed finite element software for over 20 years in a variety of R&D fields including powder metallurgy, metal forming, tire analysis and ASME Section III code applications. Since joining INL in 2015, he has worked as a developer on the BISON fuel performance code.<div class="ExternalClass69B93E4A5C2248A69EBAC6CB8735527A"><p>​Ph.D., Materials Science - University of California, Santa Barbara</p><p>M.S., Nuclear Engineering - Purdue University</p><p>B.S., Nuclear Engineering - Purdue University</p></div>https://bios.inl.gov/BioPhotos/AlCasagranda.jpgComputational ScientistCasagrandaAl
DisplayOverrideForm.aspxhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=794DisplayOverrideForm.aspxStephanie Pitts is a computational scientist with the Computational Mechanics and Materials Department at INL. She has degrees in mechanical engineering from Washington State University (B.S. 2009, Ph.D. 2019), with a Nuclear Energy University Programs Fellowship awarded in 2010. Her research interests include modeling the mesoscale evolution of metallic microstructures in response to irradiation exposure and mechanical loading, and the connection of these models to engineering scale simulations. Since joining INL in 2015, originally as an intern, she has been a member of the Bison code development team.https://bios.inl.gov/BioPhotos/StephaniePitts.JPGComputational ScientistPittsStephanie
DisplayOverrideForm.aspxhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=795DisplayOverrideForm.aspxAdam Zabriskie is a computational scientist in with the Computational Mechanics and Materials Department at INL. He has degrees in mechanical engineering from Utah State University (B.S. 2009, M.S. 2012) and in nuclear engineering from Oregon State University (Ph.D. 2019). His research focus has mainly revolved around computational applications with a nuclear emphasis. Research topics have included a computational fluid dynamics (CFD) simulation of an ATR specimen basket and transient reactor pulse simulations with coupled multiphysics and multiscale feedback. Since joining INL as an intern in 2015, he has implemented metallic fuel related capabilities in Bison.https://bios.inl.gov/BioPhotos/AdamZabriskie.jpgComputational ScientistZabriskieAdam
Wen Jiang, Ph.D.https://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=327Wen Jiang, Ph.D.Dr. Wen Jiang is a computational scientist with the Computational Mechanics and Materials Department at INL. He received his Ph.D. in Mechanical Engineering and Materials Science from Duke University in 2015. After Ph.D., he joined INL and worked in the area of computational mechanics and materials. His research focuses on developing of numerical methods for applied mechanics problems, with a particular emphasis on the important role played by interfaces and fractures. <div class="ExternalClassEC2C62C60EBE467483EF786F52B6D3DA"><p>​<span style="line-height:107%;font-family:calibri, sans-serif;font-size:12pt;"><font color="#000000">Ph.D., Mechanical Engineering and Material Science - Duke University</font></span><span style="line-height:107%;font-family:calibri, sans-serif;font-size:12pt;"><br><font color="#000000"> </font></span><span style="line-height:107%;font-family:calibri, sans-serif;font-size:12pt;"><font color="#000000">M.S., Solid Mechanics - Beijing University of Aeronautics and Astronautics</font></span><span style="line-height:107%;font-family:calibri, sans-serif;font-size:12pt;"><br><font color="#000000"> </font></span><span style="line-height:107%;font-family:calibri, sans-serif;font-size:12pt;"><font color="#000000">B.S., Aircraft Design - Beijing University of Aeronautics and Astronautics</font></span></p></div><div class="ExternalClassEB79F50B7B0F4582B1C3A4F19E73B7C3"><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong>, B.W. Spencer, J.E. Dolbow, “Ceramic nuclear fuel fracture modeling with the extended finite element method”, <em>Engineering Fracture Mechanics</em>, accepted, 2020.<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong>, TC Hu, L.K. Aagesen, YF Zhang, “Three-dimensional phase-field modeling of porosity dependent intergranular fracture in UO<sub>2</sub>”, <em>Computational Materials Science</em>, 171, 109269, 2020<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">S. Zhang, <strong>W. Jiang</strong>, M.R. Tonks, “A new phase field fracture model for brittle materials that accounts for elastic anisotropy”, <em>Computer Methods in Applied Mechanics and Engineering</em>, 358, 112643, 2020<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">T.-Y. Kim, <strong>W. Jiang</strong>, S. Lee et al., A Nitsche-type variational formulation for the shape deformation of a single component vesicle, <em>Computer Methods in Applied Mechanics and Engineering</em>, 112661, 2019<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">A Beel, TY Kim, <strong>W. Jiang</strong>, JH Song, “Strong form-based meshfree collocation method for wind-driven ocean circulation”, <em>Computer Methods in Applied Mechanics and Engineering, </em><strong>351</strong>, 404-421, 2019</p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;line-height:15pt;">P Chakraborty, <strong>W Jiang</strong>, “Crystal plasticity-based creep model for solution-strengthened nickel-based alloys”, <em>International Journal of Materials and Structural Integrity</em>, 13(1-3), 144-159, 2019 <strong></strong></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;line-height:15pt;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">Z. Zhang, <strong>W.Jiang</strong>, J. Dolbow, B. Spencer, “A modified moment-fitted integration scheme for X-FEM applications with history dependent material data”, <em>Computational Mechanics</em>, 1-20, 2018<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">I. Balushi, <strong>W. Jiang</strong>, G. Tsogtgerel and TY. Kim, “Adaptivity of a B-spline based finite-element method for modeling wind-driven ocean circulation”, <em>Computer Methods in Applied Mechanics and Engineering</em>, 332, 1-24, 2018<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;">E. Rotundo, T. Kim, <strong>W.Jiang</strong>, L.Heltai and E.Fried, “Error estimates of B-spline based finite element method for the wind-driven ocean circulation”, <em>Journal of Scientific Computing</em>, 69, 430-459, 2016<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong>, T. Kim, “Spline-based finite-element method for the stationary quasi-geostrophic equations on arbitrary shaped coastal boundaries”, <em>Computer Methods in Applied Mechanics and Engineering, </em>299, 144-160, 2016<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong> & J. Dolbow, “Adaptive refinement of the hierarchical b-spline finite element method and data transfer scheme”, <em>International Journal for Numerical Methods in Engineering</em>, 102(3-4), 233-256, 2015<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong>, C. Annavarapu, I. Harari & J. Dolbow, “A robust Nitsche’s formulation for interface problems with spline-based finite elements”, <em>International Journal for Numerical Methods in Engineering, </em>104(7), 676-696, 2015<br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><br></p><p style="color:#201f1e;background-color:#ffffff;font-size:11pt;font-family:calibri, sans-serif;margin-bottom:0px;"><strong>W. Jiang</strong> & J.L. Yang, “Energy-absorption behavior of a metallic double-sine-wave beam under axial crushing”, <em>Thin-Walled Structures</em>, 47(11), 1168-1176, 2009<br></p><p><br></p></div>Computational mechanics;Mathematical modeling;Numerical simulationshttps://bios.inl.gov/BioPhotos/Wen%20Jiang.jpgComputational ScientistJiangWen
Danielle Petersenhttps://bios.inl.gov/Lists/Researcher/DisplayOverrideForm.aspx?ID=51Danielle PetersenDanielle Petersen received her B.S. in Nuclear Engineering from Idaho State University. Perez started working at the INL as an intern in 2006 and was hired on full time in June 2010. Starting in 2009 she spent three years working on nuclear fuel performance analysis for the reduced enrichment for research and test reactor (RERTR) program. In November 2011 she began working on the assessment effort for Bison. She is also currently working towards her MS degree in Mechanical Engineering at Idaho State University. She has also served on the executive committee of the Idaho section of the American Nuclear Society for the past 6 years. In 2012 she served as the section chairman.https://bios.inl.gov/BioPhotos/Danielle%20Perez.JPGNuclear EngineerPetersenDanielle

​​​​