Refereed Journal Publications

  1. Choi, S., & Kochunas, B. (2025). Coarse mesh finite difference acceleration of the random ray method. Annals of Nuclear Energy210, 110848. https://doi.org/10.1016/J.ANUCENE.2024.110848
  2. Jeon, S., & Kochunas, B. (2024). Verification and Validation of the VANGARD Pinwise Nodal Code with Analyses of BEAVRS. Nuclear Science and Engineering, 1–24. https://doi.org/10.1080/00295639.2024.2421095
  3. Price, D., Roskoff, N., Radaideh, M. I., & Kochunas, B. (2024). Multiphysics Modeling of Heat Pipe Microreactor with Critical Control Drum Position Search. Nuclear Science and Engineering, 1–20. https://doi.org/10.1080/00295639.2024.2409582
  4. Price, D., Barrowes, L., Wells, J., & Kochunas, B. (2024). Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding. Nuclear Technology, 1–30. https://doi.org/10.1080/00295450.2024.2369476
  5. Kinast, S., Price, D., Filippone, C., & Kochunas, B. (2024). Parametric Sensitivity Analysis of Stability Margins of Holos-Quad Microreactor. Nuclear Science and Engineering, 1–17. https://doi.org/10.1080/00295639.2024.2352661
  6. Kochunas, B., Seker, V., & Ward, A. (2024). Triangular polynomial expansion nodal method in AGREE. Annals of Nuclear Energy206, 110632. https://doi.org/10.1016/J.ANUCENE.2024.110632
  7. Price, D., Radaideh, M. I., & Kochunas, B. (2024). Simplified matching pursuits applied to 3D nuclear reactor temperature distribution construction. Applied Mathematical Modelling131, 134–158. https://doi.org/10.1016/J.APM.2024.04.011
  8. Folk, T., Srivastava, S., Price, D., Garikipati, K., & Kochunas, B. (2024). Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation. Nuclear Science and Engineering, 1–16. https://doi.org/10.1080/00295639.2023.2288308
  9. Folk, T., Srivastava, S., Price, D., Garikipati, K., & Kochunas, B. (2024). Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results. Nuclear Science and Engineering, 1–24. https://doi.org/10.1080/00295639.2024.2303544
  10. Shen, Q., & Kochunas, B. (2024). Practical considerations for the adoption of Anderson acceleration in nonlinear diffusion accelerated transport. Annals of Nuclear Energy, 199, 110330. https://doi.org/10.1016/j.anucene.2023.110330
  11. Baker, U., Garrouste, M., Choi, S., Soto, G. J., Snuggerud, R., Kochunas, B., & Lindley, B. (2023). Simulation of the NuScale SMR and Investigation of the Effect of Load-Following on Component Lifetimes. Nuclear Technology, 210(1), 1–22. https://doi.org/10.1080/00295450.2023.2216973
  12. Price, D., Roskoff, N., Radaideh, M. I., & Kochunas, B. (2023). Thermal Modeling of an eVinciTM-like heat pipe microreactor using OpenFOAM. Nuclear Engineering and Design, 415, 112709. https://doi.org/10.1016/j.nucengdes.2023.112709
  13. Kang, J., Seker, V., Ward, A., Jabaay, D., Kochunas, B., & Downar, T. (2023). Cross section generation for a conceptual horizontal, compact high temperature gas reactor. Nuclear Engineering and Technology, 56(3), 933–940. https://doi.org/10.1016/j.net.2023.11.010
  14. Shen, Q., Adamowicz, N., Choi, S., Liu, Y., & Kochunas, B. (2023). Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations. Nuclear Science and Engineering, 198(9), 1776–1805. https://doi.org/10.1080/00295639.2023.2270740
  15. Wang, J., Martin, W. R., Downar, T. J., Kochunas, B., Andrews, N. C., Gilkey, L., Walker, E. D., Collins, B. S., & Pilch, M. (2022). Code Verification and Solution Verification framework in pin-resolved neutron transport code MPACT. Annals of Nuclear Energy, 178, 109365. https://doi.org/10.1016/J.ANUCENE.2022.109365
  16. Price, D., Radaideh, M. I., & Kochunas, B. (2022). Multiobjective optimization of nuclear microreactor reactivity control system operation with swarm and evolutionary algorithms. Nuclear Engineering and Design, 393, 111776. https://doi.org/10.1016/J.NUCENGDES.2022.111776
  17. Liu, Y., Kochunas, B., Nguyen, T. N., Ley, H., & Vilim, R. (2022). Solving Sensor Assignment Problem of Nuclear Power Plant Systems by Tuning Genetic Algorithm with Bayesian Optimization. Nuclear Technology, 1–15. https://doi.org/10.1080/00295450.2022.2092357
  18. Shen, Q., & Kochunas, B. (2022). High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method. Nuclear Science and Engineering, 197(7), 1364–1385. https://doi.org/10.1080/00295639.2022.2159276
  19. Shen, Q., & Kochunas, B. (2021). A Robust Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k -Eigenvalue Calculations — I: Theory. Nuclear Science and Engineering, 195(11), 1176–1201. https://doi.org/10.1080/00295639.2021.1906585
  20. Shen, Q., Choi, S., & Kochunas, B. (2021). A Robust Relaxation-free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k –eigenvalue Calculation–II: Numerical Results. Nuclear Science and Engineering, 195(11), 1202–1235. https://doi.org/10.1080/00295639.2021.1906586
  21. Dodson, Z., Kochunas, B., & Larsen, E. (2021). The Stability of Linear Diffusion Acceleration Relative to CMFD. Journal of Nuclear Engineering, 2(4), 336–344. https://doi.org/10.3390/jne2040027
  22. Kochunas, B., & Huan, X. (2021). Digital Twin Concepts with Uncertainty for Nuclear Power Applications. Energies, 14(14), 4235. https://doi.org/10.3390/EN14144235
  23. Barr, K. E., Choi, S., Kang, J., & Kochunas, B. (2021). Verification of MPACT for the APR1400 Benchmark. Energies, 14(13), 3831. https://doi.org/10.3390/en14133831
  24. Price, D., Folk, T., Duschenes, M., Garikipati, K., Kochunas, B., (2021). Methodology for Sensitivity Analysis of Homogenized Cross-Sections to Instantaneous and Historical Lattice Conditions with Application to AP1000 ® PWR Lattice. Energies, 14(12), 3378. https://doi.org/10.3390/en14123378
  25. Shen, Q., Kochunas, B., Xu, Y., Choi, S., Downar, T., (2021). Transient Multilevel Scheme with One-Group CMFD Acceleration. Nuclear Science and Engineering, 195(7), 741–765. https://doi.org/10.1080/00295639.2020.1866388
  26. Morató, S., Kochunas, B., Miró, R., Verdú, G., Larsen, E.W., Downar, T., (2021). Lambda modes comparison for different approximations of the neutron transport equation: Diffusion, SN and SP3. Annals of Nuclear Energy 154, 108074. https://doi.org/10.1016/j.anucene.2020.108074
  27. Liu, Y., Salko, R., Kim, K.S., Wang, X., Kabelitz, M., Choi, S., Kochunas, B., Collins, B., Martin, W., (2021). Improved MPACT energy deposition and explicit heat generation coupling with CTF. Annals of Nuclear Energy 152, 107999. https://doi.org/10.1016/j.anucene.2020.107999
  28. Jarrett, M.G., Kochunas, B.M., Larsen, E.W., Downar, T.J., (2020). SP3 Limit of the 2D/1D Transport Equations with Varying Degrees of Angular Coupling.  Journal of Computational and Theoretical Transport, 49(6), 303–330. https://doi.org/10.1080/23324309.2020.1819330
  29. Liu, Y., Vaughn, K., Kochunas, B., Downar, T., (2020). Validation of Pin-Resolved Reaction Rates, Kinetics Parameters, and Linear Source MOC in MPACT. Nuclear Science and Engineering, 195(1), 50–68. https://doi.org/10.1080/00295639.2020.1780853
  30. Nguyen, T. N., Jung, Y. S., Downar, T., & Lee, C. (2019). Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC. Annals of Nuclear Energy, 129, 199–206. https://doi.org/10.1016/J.ANUCENE.2019.01.005
  31. Shen, Q., Xu, Y., & Downar, T. (2019). Stability analysis of the CMFD scheme with linear prolongation. Annals of Nuclear Energy, 129, 298–307. https://doi.org/10.1016/J.ANUCENE.2019.02.011
  32. Liu, Y., Kochunas, B., Martin, W., & Downar, T. (2019). Delayed fission energy effect on LWR normal operation and transients. Annals of Nuclear Energy, 128, 84–93. https://doi.org/10.1016/J.ANUCENE.2018.12.048
  33. Fitzgerald, A. P., Kochunas, B., Stimpson, S., & Downar, T. (2019). Spatial decomposition of structured grids for nuclear reactor simulations. Annals of Nuclear Energy, 132, 686–701. https://doi.org/10.1016/J.ANUCENE.2019.06.054
  34. Shen, Q., Wang, Y., Jabaay, D., Kochunas, B., & Downar, T. (2019). Transient analysis of C5G7-TD benchmark with MPACT. Annals of Nuclear Energy, 125, 107–120. https://doi.org/10.1016/J.ANUCENE.2018.10.049
  35. Yee, B. C., Kochunas, B., & Larsen, E. W. (2019). A Multilevel in Space and Energy Solver for 3-D Multigroup Diffusion and Coarse-Mesh Finite Difference Eigenvalue Problems. Nuclear Science and Engineering, 193(7), 722–745. https://doi.org/10.1080/00295639.2018.1562777
  36. Jarrett, M., Kochunas, B., Larsen, E., & Downar, T. (2019). Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method. Nuclear Science and Engineering, 193(12), 1291–1309. https://doi.org/10.1080/00295639.2019.1627176
  37. Jarrett, M., Kochunas, B., Larsen, E., & Downar, T. (2018). Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization. Nuclear Science and Engineering, 192(3), 219–239. https://doi.org/10.1080/00295639.2018.1507186
  38. Stimpson, S., Collins, B., & Kochunas, B. (2017). Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC. Annals of Nuclear Energy, 105. https://doi.org/10.1016/j.anucene.2017.02.024
  39. Kochunas, B., Fitzgerald, A., & Larsen, E. (2017). Fourier analysis of iteration schemes for k-eigenvalue transport problems with flux-dependent cross sections. Journal of Computational Physics, 345. https://doi.org/10.1016/j.jcp.2017.05.028
  40. Yee, B. C., Kochunas, B., & Larsen, E. W. (2017). A multilevel in space and energy solver for multigroup diffusion eigenvalue problems. Nuclear Engineering and Technology, 49(6). https://doi.org/10.1016/j.net.2017.07.014
  41. Kochunas, B., Collins, B., Stimpson, S., Salko, R., Jabaay, D., Graham, A., … Gehin, J. (2017). VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion. Nuclear Science and Engineering, 185(1), 217–231. https://doi.org/10.13182/NSE16-39
  42. Zhu, A., Kochunas, B., Xu, Y., Jarrett, M., Larsen, E., & Downar, T. (2017). Theoretical convergence rate lower bounds for variants of coarse mesh finite difference to accelerate neutron transport calculations. Nuclear Science and Engineering, 186(3). https://doi.org/10.1080/00295639.2017.1293408
  43. Yee, B. C., Kochunas, B., Larsen, E. W., & Xu, Y. (2017). Space-dependent Wielandt shifts for multigroup diffusion eigenvalue problems. Nuclear Science and Engineering, 188(2), 140–159. https://doi.org/10.1080/00295639.2017.1350001
  44. Zhu, A., Jarrett, M., Xu, Y., Kochunas, B., Larsen, E., & Downar, T. (2016). An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations. Annals of Nuclear Energy, 95. https://doi.org/10.1016/j.anucene.2016.05.004
  45. Collins, B., Stimpson, S., Kelley, B. W., Young, M. T. H., Kochunas, B., Graham, A., … Godfrey, A. (2016). Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT. Journal of Computational Physics, 326. https://doi.org/10.1016/j.jcp.2016.08.022
  46. Jarrett, M., Kochunas, B., Zhu, A., & Downar, T. (2016). Analysis of stabilization techniques for CMFD acceleration of neutron transport problems. Nuclear Science and Engineering, 184(2). https://doi.org/10.13182/NSE16-51
  47. Liu, Z., Collins, B., Kochunas, B., Downar, T., Xu, Y., & Wu, H. (2015). Theory and analysis of accuracy for the method of characteristics direction probabilities with boundary averaging. Annals of Nuclear Energy, 77. https://doi.org/10.1016/j.anucene.2014.11.016
  48. Cao, L., Gerlach, A., Xu, Y., Downar, T., & Lee, J. C. (2015). Neutronics modeling of the SPERT III E-Core critical experiments with MPACT and KENO. Annals of Nuclear Energy, 80, 207–218. https://doi.org/10.1016/J.ANUCENE.2015.02.013
  49. Liu, Z., Kochunas, B., Collins, B., Downar, T., Xu, Y., & Wu, H. (2015). Model and analysis of performance for the method of characteristics direction probabilities with boundary averaging. Progress in Nuclear Energy, 80. https://doi.org/10.1016/j.pnucene.2014.12.004
  50. Zou, L., Zhang, H., Gehin, J., & Kochunas, B. (2013). Coupled Thermal-Hydraulic/Neutronics/Crud Framework in Prediction of Crud-Induced Power Shift Phenomenon. Nuclear Technology, 183(3), 5. https://doi.org/10.13182/NT13-A19440
  51. Hursin, M., Downar, T. J., & Kochunas, B. (2012). Analysis of the core power response during a PWR rod ejection transient using the PARCS nodal code and the DeCART MOC code. Nuclear Science and Engineering, 170(2). https://doi.org/10.13182/NSE10-75