ࡱ> RTQ  -'bjbj .F`_`_- 88888LLLL\$L3Ts3u3u3u3u3u3u3$6J9f38'''3883'n88s3's3-|s/n,dFw._3303.99$s/s/98w1'''''''33]'''3''''9''''''''' X : William A. Wieselquist OAK RIDGE NATIONAL LABORATORY work: +1 (865) 574 0204 cell: +1 (865) 323 8210 ww5@ornl.gov WORK EXPERIENCE 2018-present Director SCALE Code Suite 91, Reactor and Nuclear Systems Division Director of SCALE code suite with over 6M annual funding from DOE and NRC sponsors, ~30 part-time and full-time staff contributors, and ~5000 external users. Responsibilities include driving prioritization of enhancements, allocation of staff to projects, reviewing new features and bug fixes according to the SCALE QA plan, developing shared vision with sponsors, interfacing with ORNL management and external inquiries. 2020-present Group Lead, Neutronics Group 91, Reactor and Nuclear Systems Division Manage ~12 staff, including hiring and personal development. Set policies for group meetings, status updates, mentoring, publications. Handling post-COVID challenges. Division Director: Jeremy Busby 2019-2020 Team Lead, Multiphysics 91, Reactor and Nuclear Systems Division Lead the Multiphysics team within the reactor physics group. Members responsible for significant MPACT and SCALE code development. Group Leader: Kevin Clarno 2017-2018 Senior R&D Staff, Reactor Physics Group 91, Reactor and Nuclear Systems Division Deputy Manager of SCALE code package. Research in depletion, lattice physics, and UQ methods for high-performance computing (HPC). Group Leader: Kevin Clarno 2012-2017 Reactor Physics Group Staff 91, Reactor and Nuclear Systems Division Code manager and lead developer for ORIGEN decay/depletion/activation code, Sampler uncertainty quantification (UQ) code. Research in fast depletion and UQ methods for high-performance computing (HPC). Group Leader: Stephen Bowman 2009-2012 Staff Scientist Paul Scherrer Institut, Laboratory for Reactor Systems Maintained/updated/validated core-follow models for Swiss nuclear power plants based on CASMO-5/SIMULATE-3 with the STARS Project, developed a sampling-based uncertainty quantification platform for the CASMO-5 lattice physics code, supervised interns and master's students in the Swiss nuclear engineering programs including teaching the first year of a masters level computational neutronics course, worked on additional projects for the Swiss nuclear regulatory agency, ENSI. Group Leader: Hakim Ferroukhi PROFESSIONAL ACTIVITIES Assistant Technical Program Chair for ANS M&C 2021 in Raleigh, NC. Peer reviewer for journals: Annals of Nuclear Energy and Science and Technology of Nuclear Installations in uncertainty quantification methods. Active reviewer for ANS M&C and PHYSOR conferences in deterministic transport and uncertainty quantification. EDUCATION 2005-2008 Ph.D. Nuclear Engineering, North Carolina State University. The Quasidiffusion Method for Transport Problems on Unstructured Meshes 3.71 GPA, Mathematics minor. 2005 M.S. Nuclear Engineering, North Carolina State University. The New Nuclear Data Sensitivity Analysis and Uncertainty Propagation Tool in NESTLE 3.71 GPA, Mathematics minor. 2002 B.S. Nuclear Engineering, North Carolina State University. 3.78 GPA summa cum laude, German minor. HONORS AND AWARDS Federal Laboratory Consortium for Technology Transfer (FLC) Southeast Region for Licensing SCALE 6.2: a software package for nuclear safety analysis and design (2018) ORNL Achievement Award for depletion work in DOE-CASL project (2014) Best Student Paper Award at M&C 2009, Saratoga Springs, NY (2009) Advanced Fuel Cycle Initiative (AFCI) Fellowship (2002-2005) Best Thermal-Hydraulics Paper in Student Section of 10th International Conference on Nuclear Engineering (ICONE), Arlington, VA, April 14-18 (2002) Outstanding Undergraduate Award, North Carolina State University (2002) MEMBER SOCIETIES American Nuclear Society Member (2002-present); Tau Beta Pi, Engineering Honors Society (2002); National Society of Collegiate Scholars (2002). SELECTED PUBLICATIONS Friederike Bostelmann, Cihangir Celik, Mark L. Williams, Ronald J. Ellis, Germina Ilas, William A. Wieselquist, SCALE capabilities for high temperature gas-cooled reactor analysis, Annals of Nuclear Energy, vol. 147 (2020). Pedro Valdez, Benjamin R. Betzler, William A. Wieselquist, Massimiliano Fratoni, Modeling Molten Salt Reactor Fission Product Removal with SCALE, ORNL/TM-2019/1418 (2020). Majdi I. Radaideh,Tomasz Kozlowski,William A. Wieselquist,andMatthew A. Jessee, Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark, Science and Technology of Nuclear Installations, vol 2019 (2019). W. Wieselquist, M. Williams, D. Wiarda, M. Pigni, and U. Mertyurek, Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis, NUREG/CR-7249, ORNL/TM-2017/706 (2018). Gregory G. Davidson, Tara M. Pandya, Seth R. Johnson, Thomas M. Evans, Aarno E. Isotalo, Cole A. Gentry, William A. Wieselquist, Nuclide depletion capabilities in the Shift Monte Carlo code, Annals of Nuclear Energy, vol.114 (2018). Ryan N. Bratton, Matt A. Jessee, William A. Wieselquist & Kostadin N. Ivanov, Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON,Nuclear Technology,197:1,47-63 (2017). Brendan Kochunas, Benjamin Collins, Shane Stimpson, Robert Salko, Daniel Jabaay, AaronGraham, Yuxuan Liu, Kang Seog Kim, William Wieselquist, Andrew Godfrey, Kevin Clarno,Scott Palmtag, Thomas Downar, and Jess Gehin, VERA core simulator methodology for pressurized water reactor cycle depletion, Nuclear Science and Engineering, vol. 185 (2017). J. Peterson, E. Sunny, W. Wieselquist, A. Worrall, and R. Gregg, Generating cross sections for ORION fuel cycle models, Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, vol. 4 (2016). A.E. Isotalo, G.G. Davidson, T.M. Pandya, W.A. Wieselquist, and S.R. Johnson, Flux renormalization in constant power burnup calculations, Annals of Nuclear Energy, vol. 96, pp. 148-157 (2016). A.E. Isotalo and W.A. Wieselquist, A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN, Annals of Nuclear Energy, vol. 85, pp. 68-77 (2015). B. Kochunas, B. Collins, D. Jabaay, S. Stimpson, A. Graham, K.S. Kim, W. Wieselquist, K. Clarno, S. Palmtag, T. Downar, and J. Gehin, Vera core simulator methodology for PWR cycle depletion, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference M&C+SNA+MC 2015, vol. 1, pp. 660-673 (2015). W.A. Wieselquist, D.Y. Anistratov, and J.E. Morel, A cell-local finite difference discretization of the low-order quasidiffusion equations for neutral particle transport on unstructured quadrilateral meshes, Journal of Computational Physics, vol. 273, pp. 343-357 (2014). T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, and A. Pautz, Comparison of two approaches for nuclear data uncertainty propagation in MCNPX for selected fast spectrum critical benchmarks, Nuclear Data Sheets, vol. 118, pp. 388-391 (2014). W. Wieselquist, T. Zhu, V. Vasiliev, and H. Ferroukhi. PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I, Science and Technology of Nuclear Installations (2013). W. Wieselquist, V. Vasiliev, and H. Ferroukhi. 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