Refereed Conference Proceedings

Nuclear Reactor Analysis & Methods/Publications/Refereed Conference Proceedings

2025


    • …and more!

    2024

    • Vaughn, K., & Kochunas, B. (2024). Assessment of Heuristics for the Automated Generation of 2D Method of Characteristics Mesh. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 423–431. https://doi.org/10.13182/PHYSOR24-43572
    • Jayasankar, T., Price, D., Radaideh, M. I., & Kochunas, B. (2024). Scalarized Multiobjective Fuel Loading Optimization of Extended-Cycle NuScale Power Module with Evolutionary Algorithms. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 2500–2509. https://doi.org/10.13182/PHYSOR24-43473
    • Choi, S., Shen, Q., Filippone, C., & Kochunas, B. (2024). Comparative Analysis on the Passive Flow Rate Control in the Load-Follow Simulation for Holos-Quad Microreactor. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 2206–2215. https://doi.org/10.13182/PHYSOR24-43476
    • Shen, Q., & Kochunas, B. (2024). Hybrid Reduced-Order Modeling based on Reduced Basis and PCQM Methods for Time-dependent Diffusion Problem with Cross Section Feedback. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 1652–1661. https://doi.org/10.13182/PHYSOR24-43530
    • Price, D., Radaideh, M. I., & Kochunas, B. (2024). Application of Basis Projection Methods to Temperature Distribution Construction in Heat Pipe Microreactor. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 872–881. https://doi.org/10.13182/PHYSOR24-43479
    • Mager, T., Vaughn, K., Hursin, M., Kochunas, B., & Pautz, A. (2024). Preliminary Validation of Intra-pin Reaction Rate Predictions from the Deterministic Transport Codes GeN-Foam and MPACT. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 768–777. https://doi.org/10.13182/PHYSOR24-43646
    • Folk, T., & Kochunas, B. (2024). Derivation of the History Variable Calculation for Macro-depletion in Nodal Simulators. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 632–641. https://doi.org/10.13182/PHYSOR24-43875
    • Jeon, S., & Kochunas, B. (2024). Verification and Validation of the VANGARD Pinwise Nodal Code with Preliminary Analyses of BEAVRS Benchmark. Proceedings of the International Conference on Physics of Reactors (PHYSOR 2024), 790–799. https://doi.org/10.13182/PHYSOR24-43453
    • Shen, Q., Farha, F., Piper, S., & Kochunas, B. (2024). Development of the Dynamics Model of a Horizontal Compact High Temperature Gas Reactor (HC-HTGR) in Modelica. Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2024), 185–194. https://doi.org/10.13182/T130-44234

    2023

    • Folk, T., Godfrey, A., & Kochunas, B. (2023, August 14). MxN Reflector Cross Section Sensitivity and Functionalization. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Folk, T., Ward, A., & Kochunas, B. (2023, August 14). Application of MPACT to Generate Few-Group Cross Sections for PARCS. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Kabelitz, M., Shen, Q., & Kochunas, B. (2023, August 14). Development of a Fast Solver for Multi-Dimensional Low-Order Transport. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Vaughn, K., & Kochunas, B. (2023, August 14). Heuristics for the Automatic Generation of Unstructured Mesh for Method of Characteristics Calculations. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Shen, Q., Choi, S., & Kochunas, B. (2023, August 14). Demonstration of Autonomous Control in High-Fidelity Simulations for Load Follow Transients with MPACT. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Kinast, S., Price, D., Sivan, D., Filippone, C., & Kochunas, B. (2023, August 14). Sensitivity Study of Stability Margins of HTR-Type Microreactor. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Price, D., Roskoff, N., Radaideh, M., & Kochunas, B. (2023, August 14). Serpent-OpenFOAM Coupling of an eVinci TM Motivated Microreactor Design for Burnup-Dependent Critical Drum Positions. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Choi, S., Shen, Q., Lee, C. H., Filippone, C., & Kochunas, B. (2023, August 14). Preliminary Results of Load Follow Simulation for Holos-Quad Microreactor using PROTEUS and Model Predictive Control. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023).
    • Price, D., Radaideh, M. I., & Kochunas, B. (2023). Active Learning with Deep Neural Network Ensembles for Heat Pipe Microreactor Modeling in Abnormal Operation. Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023, 355–364. https://doi.org/10.13182/PSA23-41214
    • Kang, J., Seker, V., Ward, A., Jabaay, D., Kochunas, B., & Downar, T. (2023, April 23). Cross Section Generation for a Conceptual Horizontal, Compact High Temperature Gas Reactor. Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAAP 2023).

    2022

    • Baker, U., Garrouste, M., Choi, S., Soto, G. J., Lindley, B., & Kochunas, B. (2022). Development of a High-fidelity Multi-cycle Model of the NuScale Small Modular Reactor Using VERA. PHYSOR2022 – International Conference on Physics of Reactors, 1550–1559.
      https://doi.org/10.13182/PHYSOR22-37328
    • Choi, S., & Kochunas, B. (2022). PN Source Expansion Nodal Method in MPACT for Boiling Water Reactors. PHYSOR2022 – International Conference on Physics of Reactors, 1214–1223. https://doi.org/10.13182/PHYSOR22-37363
    • Choi, S., Ward, A., Graham, A., Collins, B., Kochunas, B., & Asgari, M. (2022). Preliminary Simulation Results of Peach Bottom Unit 2 Cycles 1 and 2 with MPACT. PHYSOR2022 – International Conference on Physics of Reactors, 2316–2325. https://doi.org/10.13182/PHYSOR22-37699
    • Folk, T., Srivastava, S., Price, D., Kochunas, B., & Garikipati, K. (2022a). Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-I: Theory. PHYSOR2022 – International Conference on Physics of Reactors, 1256–1265. https://doi.org/10.13182/PHYSOR22-37828
    • Folk, T., Srivastava, S., Price, D., Kochunas, B., & Garikipati, K. (2022b). Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-II: Numerical Results. PHYSOR2022 – International Conference on Physics of Reactors, 1266–1275.
      https://doi.org/10.13182/PHYSOR22-37832
    • Hursin, M., Mala, P., Vasiliev, A., Ferroukhi, H., Liu, Y., Choi, S., & Kochunas, B. (2022). Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices. PHYSOR2022 – International Conference on Physics of Reactors, 2762–2772.
      https://doi.org/10.13182/PHYSOR22-37760
    • Kinast, S., Filippone, C., & Kochunas, B. (2022). Stability Margin Analysis of the Holos-Quad Microreactor Design. PHYSOR2022 – International Conference on Physics of Reactors, 78–86. https://doi.org/10.13182/PHYSOR22-37918
    • Liu, Y., Jabaay, D., Kochunas, B., & Kim, K. S. (2022). Validation of MPACT BWR Capabilities Against Critical Experiments. PHYSOR2022 – International Conference on Physics of Reactors, 1047–1056. https://doi.org/10.13182/PHYSOR22-37393
    • Price, D., Folk, T., Srivastava, S., Garikipati, K., & Kochunas, B. (2022). Sensitivity Analysis of Homogenized Cross Sections in AP1000 ® Lattices. PHYSOR2022 – International Conference on Physics of Reactors, 1286–1295. https://doi.org/10.13182/PHYSOR22-37383
    • Price, D., Kinast, S., & Kochunas, B. (2022). Error Analysis of a Hybrid Control Drum Worth Model. PHYSOR2022 – International Conference on Physics of Reactors, 1627–1636. https://doi.org/10.13182/PHYSOR22-37381
    • Shen, Q., & Kochunas, B. (2022a). Anderson Acceleration Stability in NDA-accelerated k-Eigenvalue Problems. PHYSOR2022 – International Conference on Physics of Reactors, 36–45. https://doi.org/10.13182/PHYSOR22-37782
    • Shen, Q., & Kochunas, B. (2022b). High-order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method. PHYSOR2022 – International Conference on Physics of Reactors, 846–855. https://doi.org/10.13182/PHYSOR22-37781
    • Yokoi, K., Hino, T., Ishii, K., Miwa, J., Soneda, H., Kowalski, M. A., Shwageraus, E., Kochunas, B., Choi, S., Liu, Y., & Nagaya, Y. (2022). Applicability of Neutronics Design Calculation Method for Axially Heterogeneous Core of RBWR (Resource-renewable Boiling Water Reactor). PHYSOR2022 – International Conference on Physics of Reactors, 2326–2335.
      https://doi.org/10.13182/PHYSOR22-37279

    2021

    • Barr, K., Choi, S., & Kochunas, B. (2021). VERIFICATION OF MPACT AND VERA-CS FOR THE APR1400 BENCHMARK. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 1911–1923. https://doi.org/10.13182/M&C21-33686
    • Choi, S., Kinast, S., Filippone, C., & Kochunas, B. (2021). COMPARATIVE STUDY FOR LOAD-FOLLOW OPERATIONS OF THE HOLOS MICROREACTOR. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 728–737. https://doi.org/10.13182/M&C21-33733
    • Choi, S., & Kochunas, B. (2021). THE LIMITED LINEAR SOURCE APPROXIMATION OF THE METHOD OF CHARACTERISTICS FOR MITIGATING NEGATIVE SOURCES. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 178–187. https://doi.org/10.13182/M&C21-33635
    • Dodson, Z., Kochunas, B., & Larsen, E. (2021). FOURIER ANALYSIS OF COARSE MESH FINITE DIFFERENCE AND LINEAR DIFFUSION ACCELERATION FOR SPATIALLY HETEROGENEOUS SYSTEMS. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 1084–1094.
      https://doi.org/10.13182/M&C21-33868
    • Kabelitz, M., & Kochunas, B. (2021). UNIFYING THE FINITE ELEMENT AND NODAL EXPANSION METHODS UNDER THE WEIGHTED RESIDUALS FRAMEWORK. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 908–917. https://doi.org/10.13182/M&C21-33874
    • Kinast, S., Sivan, D., Choi, S., Filippone, C., & Kochunas, B. (2021). FREQUENCY DOMAIN ANALYSIS OF HTR-LIKE MICROREACTORS. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 1517–1527. https://doi.org/10.13182/M&C21-33807
    • Li, J., Kinast, S., Seker, V., Wang, J., Ward, A., Kochunas, B., Downar, T., & Mertyurek, U. (2021). NEUTRONICS SIMULATION OF THE MOLTEN SALT REACTOR EXPERIMENT WITH SCALE/SHIFT AND SERPENT/PARCS. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 530–539. https://doi.org/10.13182/M&C21-33739
    • Liu, Y., Kochunas, B., Nguyen, T. N., Ley, H., & Vilim, R. (2021). A Parallel Capability Using Genetic Algorithm for Sensor Assignment Optimization with Process-Constrained Data-Analytic Diagnosis. 12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021), 1164–1174. https://doi.org/10.13182/T124-35388
    • Shen, Q., Choi, S., & Kochunas, B. (2021). Robust Relaxation-free Multiphysics Simulation via Power-Iteration-Level-Coupled CMFD Acceleration in MPACT. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 2064–2073. https://doi.org/10.13182/M&C21-33715
    • Vaughn, K., & Kochunas, B. (2021). PRELIMINARY INVESTIGATION OF ARBITRARY CAD GEOMETRY AND UNSTRUCTURED MESH WITH 2D METHOD OF CHARACTERISTICS IN MPACT. Proceedings of The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021), 1709–1718. https://doi.org/10.13182/M&C21-33780

    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 https://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 https://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 https://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 https://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 https://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.