NUclear Reactor Analysis & Methods > Publications > PhD Dissertations

PhD Dissertations

  1. Shen, Q. (2021). Robust and Efficient Methods in Transient Whole-Core Neutron Transport Calculations (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/168050
  2. Gerlach, A. (2020). Adaptive Time Stepping for Transport Solution with the α-Eigenvalue (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/155190
  3. Fitzgerald, A. (2019). Parallel 3-D Method of Characteristics with Linear Source and Advanced Transverse Integration (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/155260
  4. Nguyen, T. (2019). Model-Based Diagnostic Frameworks for Fault Detection and System Monitoring in Nuclear Engineering Systems (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/155193
  5. Wang, J. (2019). Application of the Method of Manufactured Solutions to Verify the Method of Characteristics for Reactor Analysis (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/151621
  6. Zhou, H. (2019). Sparse Functional Expansion Based Method for Solving High-dimensional Uncertainty Quantification Problems and Its Application to the Nuclear Transient Test Reactor (TREAT) (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/151420
  7. Jarrett, M. (2018). A 2D/1D Neutron Transport Method with Improved Angular Coupling (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/147498
  8. Yee, B. (2018). A Multilevel in Space and Energy Solver for Multigroup Diffusion and Coarse Mesh Finite Difference Eigenvalue Problems (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/146075
  9. Graham, A. (2017). Subgrid Methods for Resolving Axial Heterogeneity in Planar Synthesis Solutions for the Boltzmann Transport Equation (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/138586
  10. Rose, M. (2017). Multiphysics Simulation of Fission Gas Production and Release in Light Water Reactor Fuel (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/140807
  11. Walter, D. (2016). A High Fidelity Multiphysics Framework for Modeling CRUD Deposition on PWR Fuel Rods (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/120638
  12. Young, M. (2016). Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/135759
  13. Zhu, A. (2016). Transient Methods for Pin-Resolved Whole Core Transport (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/133353
  14. Bielen, A. (2015). Sensitivity and Uncertainty Analysis of Multiphysics Nuclear Reactor Core Depletion (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/111444
  15. Hall, A. (2015). Homogenization Methods for Full Core Solution of the Pn Transport Equations with 3-D Cross Sections (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/116697
  16. Kelley, B. (2015). An Investigation of 2D/1D Approximations to the 3D Boltzmann Transport Equation (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/113576
  17. Liu, Y. (2015). A Full Core Resonance Self-shielding Method Accounting for Temperature-dependent Fuel Subregions and Resonance Interference (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/111419
  18. Saller, T. (2015). Asymptotic Homogenized SP2 Approximations to the Neutron Transport Equation (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/116754
  19. Stimpson, S. (2015). An Azimuthal Fourier Moment-Based Axial SN Solver for the 2D/1D Scheme (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/111446
  20. Wysocki, A. (2015). Investigation of Limit Cycle Behavior in BWRs with Time-Domain Analysis (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/111374
  21. Yankov, A. (2015). Analysis of Reactor Simulations Using Surrogate Models (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/111485
  22. Trahan, T. (2014). An Asymptotic, Homogenized, Anisotropic, Multigroup Diffusion Approximation to the Neutron Transport Equation (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/107152
  23. Kochunas, B. (2013). A Hybrid Parallel Algorithm for the 3-D Method of Characteristics Solution of the Boltzmann Transport Equation on High Performance Compute Clusters (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/100072
  24. Ward, A. (2012). A Newton-Krylov Solution to the Coupled Neutronics-Porous Medium Equations (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/91609
  25. Collins. B. (2011). Multiscale Methods for Nuclear Reactor Analysis (Doctoral Dissertation) University of Michigan, Ann Arbor, MI. http://hdl.handle.net/2027.42/89812