NUclear Reactor Analysis & Methods > Publications > Refereed Conference Proceedings

Refereed Conference Proceedings

2020

  • Li, J., Xu, Y., Wang, D., Shen, Q., Kochunas, B., & Downar, T. (2020). Demonstration of a Linear Prolongation CMFD Method on MOC. In PHYSOR 2020 – Transition to a Scalable Nuclear Future (accepted). Cambridge, UK: American Nuclear Society. https://drive.google.com/file/d/1MpmgCWVmStaJEXdXWvK43yMOHDh0UZx2/view?usp=sharing
  • Dodson, Z., Kochunas, B., & Larsen, E. (2020). The Stability of Linear Diffusion Acceleration Relative to CMFD. In PHYSOR 2020 – Transition to a Scalable Nuclear Future. Cambridge, UK: American Nuclear Society.
  • Herring, N. F., Fitzgerald, A., Kochunas, B., & Downar, T. (2020). Improved Anisotropic Linear Source Formulation for Multiphysics Problems. In PHYSOR 2020 – Transition to a Scalable Nuclear Future. Cambridge, UK: American Nuclear Society.
  • Shen, Q., Kochunas, B., & Downar, T. (2020). Efficient Multiphysics Iterations in MPACT with Partially Convergent CMFD. In PHYSOR 2020 – Transition to a Scalable Nuclear Future. Cambridge, UK: American Nuclear Society. https://drive.google.com/file/d/1ECprm6gBaKX9auV5OVHQRnuXuqdV3e4H/view?usp=sharing
  • Liu, Y., Salko R., Kim K.S., Wang, X., Kabelitz, M., Kochunas, B., Collins, B., Martin, W., (2020) An Improved Energy Deposition Model in MPACT and Explicit Heat Generation Coupling with CTF.  In PHYSOR 2020 – Transition to a Scalable Nuclear Future. Cambridge, UK: American Nuclear Society. https://drive.google.com/file/d/1_xiiZQEoY1D22doQqRWGFPr9O8Sf9hFL/view?usp=sharing

2019

  • Shen, Q., Adamowicz, N., Kochunas, B., & Larsen, E. (2019). X-CMFD: A Robust Iteration Scheme for CMFD-Based Acceleration of Neutron Transport Problems with Nonlinear Feedback. In M&C 2019 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (pp. 2238–2247). Portland, OR: American Nuclear Society. Retrieved from http://epubs.ans.org/?a=46805
  • Fitzgerald, A. P., Kochunas, B., & Downar, T. (2019). Improved Formulation of the Method of Characteristics with Linear Source for 2D/1D and Multiphysics Calculations. In M&C 2019 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (pp. 1093–1103). Portland, OR: American Nuclear Society. Retrieved from http://epubs.ans.org/?a=46694
  • Kochunas, B. (2019). Theoretical Convergence Rate Analysis of a Unified CMFD Formulation with Various Diffusion Coefficients. In M&C 2019 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (pp. 978–990). Portland, OR: American Nuclear Society. Retrieved from http://epubs.ans.org/?a=46683
  • Dodson, Z., Adamowicz, N., Kochunas, B., & Larsen, E. (2019). SDA: A SEMILINEAR CMFD-LIKE TRANSPORT ACCELERATION SCHEME WITHOUT D-hat. In M&C 2019 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (pp. 1714–1723). Portland, OR: American Nuclear Society. Retrieved from http://epubs.ans.org/?a=46755
  • Shen, Q., Adamowicz, N., & Kochunas, B. (2019). Relationship Between Relaxation and Partial Convergence of Nonlinear Diffusion Acceleration for Problems with Feedback. In M&C 2019 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (pp. 2248–2257). Portland, OR: American Nuclear Society. Retrieved from http://epubs.ans.org/?a=46806

2018

  • Jarrett, M., Kochunas, B., Larsen, E., & Downar, T. (2018). An Improved 2D/1D P 3 Method with Angle-dependent Leakage and Pin Homogenization. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Kucukboyaci, V. N., Kochunas, B., Downar, T. J., Wysocki, A., & Salko, R. K. (2018). EVALUATION OF VERA-CS TRANSIENT CAPABILITY FOR ANALYZING THE AP1000 ® REACTOR CONTROL ROD EJECTION ACCIDENT. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Xu, Y., Hao, C., & Downar, T. J. (2018). A REDUCED SOR PRECONDITIONER FOR THE GMRES SOLUTION OF THE COARSE MESH FINITE DIFFERENCE EQUATIONS. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Liu, Y., Martin, W., & Downar, T. (2018). Delayed Fission Energy Effect on LWR Normal Operation and Transients. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Shen, Q., Kochunas, B., Xu, Y., & Downar, T. (2018). TRANSIENT MULTILEVEL SCHEME WITH ONE GROUP CMFD ACCELERATION. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Dodson, Z., Yee, B. C., Kochunas, B., Downar, T., & Kim, K. S. (2018). PROGRESS IN VALIDATION OF MPACT WITH CRITICAL EXPERIMENTS. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.
  • Yee, B. C., Kochunas, B., & Larsen, E. W. (2018). A MULTILEVEL DIFFUSION SOLVER FOR MULTI-DIMENSIONAL TRANSPORT PROBLEMS WITH CMFD. In PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems. Cancun, Mexico: American Nuclear Society.

2017

  • Kochunas, B., Zhu, A., Jabaay, D., Xu, Y., & Downar, T. (2017). Whole-Core Pin-Resolved PWR Transient Calculations in MPACT. In M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: American Nuclear Society.
  • Kochunas, B., Jabaay, D., Fitzgerald, A., Downar, T. J., & Palmtag, S. (2017). Initial BWR Modeling Capability for MPACT. In M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: American Nuclear Society.
  • Jarrett, M., Kochunas, B., Larsen, E., & Downar, T. (2017). Characterization of 2D/1D Accuracy in MPACT. In M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: American Nuclear Society.
  • Yee, B. C., Kochunas, B., & Larsen, E. W. (2017). A Multilevel in Space and Energy Solver for Multigroup Diffusion Eigenvalue Problems. In M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: American Nuclear Society.
  • Palmtag, S., Kochunas, B., Jabaay, D., Han, Z., & Downar, T. (2017). Modeling Thermal Expansion in VERA-CS. In M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: American Nuclear Society.

2016

  • Downar, T., Kochunas, B., & Collins, B. (2016). Validation and Verification of the MPACT Code. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, Idaho, USA: American Nuclear Society.
  • Eyers, B. D., Wu, Z., & Kochunas, B. (2016). FEASIBILITY INVESTIGATION OF APPLICATION OF MPACT TO CORE DESIGN STUDIES OF NBSR-2, A HEAVY WATER-REFLECTED, HETEROGENEOUS LEU FUEL RESEARCH REACTOR. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, Idaho, USA: American Nuclear Society.
  • Kochunas, B., & Larsen, E. (2016). Fourier Analysis of Iteration Schemes for k-eigenvalue Transport Problems with Flux-Dependent Cross Sections. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, ID, USA: American Nuclear Society.
  • Godfrey, A., Collins, B., Seog Kim, K., Powers, J., Salko, R., Stimpson, S., … Secker, J. (2016). VERA BENCHMARKING RESULTS FOR WATTS BAR NUCLEAR PLANT UNIT 1 CYCLES 1-12. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, Idaho, USA: American Nuclear Society.
  • Graham, A., Downar, T., Collins, B., Salko, R., & Palmtag, S. (2016). ASSESSMENT OF THERMAL-HYDRAULIC FEEDBACK MODELS. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, Idaho, USA: American Nuclear Society.
  • Yee, B. C., Larsen, E. W., & Kochunas, B. (2016). An Analytical Derivation of Transport-Corrected P 0 Cross Sections and Diffusion Coefficients. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, ID, USA: American Nuclear Society.
  • Stimpson, S. G., & Collins, B. S. (2016). ADVANCED NODAL P 3 /SP 3 AXIAL TRANSPORT SOLVERS FOR THE MPACT 2D/1D SCHEME. In PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century. Sun Valley, Idaho, USA: American Nuclear Society.

2015

  • Clarno, K. T., Pawlowski, R. P., Montgomery, R. O., Evans, T. M., Collins, B. S., Kochunas, B., … Turner, J. A. (2015). High Fidelity Modeling of Pellet-Clad Interactions Using the CASL Virtual Environment for Reactor Applications. In M&C 2015 – Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. Nasvhille, TN: American Nuclear Society.
  • Kochunas, B., & Downar, T. (2015). Performance Model Development and Analysis for the 3-D Method of Characteristics. In M&C 2015 – Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. Nashville, Tennessee, USA: American Nuclear Society.
  • Kochunas, B., Collins, B., Jabaay, D., Stimpson, S., Graham, A., Seog Kim, K., … Gehin, J. (2015). VERA Core Simulator Methodology for PWR Cycle Depletion. In M&C 2015 – Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. Nashville, Tennessee, USA: American Nuclear Society.
  • Jarrett, M., Kelley, B., Kochunas, B., Downar, T., & Larsen, E. (2015). Stabilization Methods for CMFD Acceleration. In M&C 2015 – Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. Nashville, Tennessee, USA: American Nuclear Society.

2014

  • Kochunas, B., Jabaay, D., Collins, B., & Downar, T. (2014). COUPLED THERMAL-HYDRAULICS AND NEUTRONICS CALCULATIONS WITH COBRA-TF AND MPACT. In ATH ’14 – Advances in Thermal Hydraulics 2014. Reno, NV: American Nuclear Society.
  • Zhu, A., Collins, B., Kochunas, B., & Downar, T. (2014). Assessment of the Depletion Capability in MPACT. In PHYSOR 2014 – The Role ofReactor Physics toward a Sustainable Future. Kyoto, Japan: American Nuclear Society.
  • Kochunas, B., Kelley, B. W., Stimpson, S. G., Larsen, E., & Downar, T. J. (2014). Application of the SDD-CMFD Acceleration Method to Parallel 3-D MOC Transport. In PHYSOR 2014 – The Role ofReactor Physics toward a Sustainable Future. Kyoto, Japan: American Nuclear Society.
  • Stimpson, S. G., Collins, B. S., & Downar, T. J. (2014). Axial Transport Solvers for the 2D/1D Scheme in MPACT. In PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future. Kyoto, Japan: American Nuclear Society.
  • Stimpson, S. G., Collins, B. S., Kochunas, B. M., & Downar, T. J. (2014). Boundary Acceleration Techniques for CMFD-accelerated 2D-MOC. In PHYSOR 2014 – The Role ofReactor Physics toward a Sustainable Future. Kyoto, Japan: American Nuclear Society.

2013

  • Kochunas, B., Downar, T. J., & Liu, Z. (2013). PARALLEL 3-D METHOD OF CHARACTERISTICS IN MPACT. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Liu, Z., Kochunas, B., Collins, B., Downar, T., & Wang, H. (2013). THE METHOD OF MODULAR CHARACTERISTIC DIRECTION PROBABILITIES IN MPACT. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Liu, Y., Martin, W., Kim, K.-S., & Williams, M. (2013). MODELING RESONANCE INTERFERENCE BY 0-D SLOWING-DOWN SOLUTION WITH EMBEDDED SELF-SHIELDING METHOD. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Kelley, B. W., & Larsen, E. W. (2013). 2D/1D APPROXIMATIONS TO THE 3D NEUTRON TRANSPORT EQUATION. I: THEORY. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Liu, Y., Collins, B., Kochunas, B., Martin, W., Kim, K.-S., & Williams, M. (2013). Resonance self-shielding methodology in MPACT. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Kochunas, B., Collins, B., Jabaay, D., Downar, T. J., & Martin, W. R. (2013). Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Kelley, B. W., Collins, B., & Larsen, E. W. (2013). 2D/1D APPROXIMATIONS TO THE NEUTRON TRANSPORT EQUATION. II: NUMERICAL RESULTS. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.
  • Collins, B., Kochunas, B., & Downar, T. (2013). Assessment of the 2D MOC solver in MPACT: Michigan parallel characteristics transport code. In M&C 2013 – International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley, Idaho, USA: American Nuclear Society.

2012

  • Zou, L., Zhang, H., Gehin, J., & Kochunas, B. (2012). A COUPLED TH/NEUTRONICS/CRUD FRAMEWORK IN PREDICTION OF CIPS PHENOMENON. In PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education. Knoxville, TN, USA: American Nuclear Society.
  • Kochunas, B., Downar, T., & Taiwo, T. (2012). EQUILIBRIUM CYCLE PIN BY PIN TRANSPORT DEPLETION CALCULATIONS WITH DeCART. In PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education. Knoxville, TN, USA: American Nuclear Society.
  • Kelley, B. W., & Larsen, E. W. (2012). CMFD Acceleration of Spatial Domain-Decomposed Neutron Transport Problems. In PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education. Knoxville, TN, USA: American Nuclear Society.
  • Xu, Y., & Downar, T. (2012). Convergence Analysis of a CMFD Method Based on Generalized Equivalence Theory. In PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education. Knoxville, TN, USA: American Nuclear Society.
  • Kochunas, B., Stimpson, S., Collins, B., Downar, T., Brewster, R., & Baglietto, E. (2012). Coupled Full Core Neutron Transport/CFD Simulations of Pressurized Water Reactors. In PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education. Knoxville, TN, USA: American Nuclear Society.

2011

  • Yan, J., Kochunas, B., Hursin, M., Downar, T., Karoutas, Z., & Baglietto, E. (2011). Coupled Computational Fluid Dynamics and MOC Neutronic Simulations of Westinghouse PWR Fuel Assemblies with Grid Spacers. In NURETH-14 – International Topical Meeting on Nuclear Reactor Thermalhydraulics. Toronto, Ontario, CA: American Nuclear Society.

2010

  • Kochunas, B., Xu, Y., & Downar, T. (2010). Development of the Triangular Nodal Method TRIPEN for Prismatic VHTR Analysis. In PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance. Pittsburgh, Pennsylvania, USA: American Nuclear Society.
  • Hursin, M., Downar, T. J., & Kochunas, B. (2010). Consistent Comparison of Full Core PWR Reactivity Initiated Accident with the Method Of Characteristic Code DeCART and the Coarse Mesh Nodal Code PARCS. In PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance. Pittsburgh, Pennsylvania, USA: American Nuclear Society.