Publications


Third-party Technical Reports

This subsection lists technical reports primarily concerned with the topic of radiation transport on unstructured mesh. It is partly, but not exclusively, a selection of reports from the MCNP Reference Collection page. These reports tend to be longer and more detailed than the peer-reviewed publications in the following section, but unlike those publications, these reports do not generally undergo independent peer review.

  1. J. L. ALWIN and J. B. SPENCER, “Critical Experiment Benchmark Results Using MCNP6.2 Unstructured Mesh,” LA-UR-19-29093, Los Alamos National Laboratory, Los Alamos, NM, USA (2019); doi:10.2172/1565798
  2. J. L. ALWIN, J. B. SPENCER and G. FAILLA, “Criticality Accident Alarm System (CAAS) CSG-UM Hybrid Example,” LA-UR-19-27007, Los Alamos National Laboratory, Los Alamos, NM, USA (2019); doi:10.2172/1544654
  3. J. L. ALWIN and J. B. SPENCER, “Critical Experiment Benchmark Results Using UM and Mesh Quality Recommendations,” LA-UR-19-26393, Los Alamos National Laboratory, Los Alamos, NM, USA (2019); doi:10.2172/1532696
  4. J. B. SPENCER and J. L. ALWIN, “Big Ten MCNP6 Unstructured Mesh Benchmark,” LA-UR-19-25731, Los Alamos National Laboratory, Los Alamos, NM, USA (2019); doi:10.2172/1529515
  5. J. L. ALWIN, J. B. SPENCER and G. FAILLA, “Criticality Accident Alarm System Analysis Using MCNP6.2 Constructive Solid Geometry/Unstructured Mesh Hybrid,” LA-UR-19-24892, Los Alamos National Laboratory, Los Alamos, NM, USA (2019); URL
    Also published as a Peer-reviewed Publication (see #4 below).
  6. R. L. MARTZ, “The MCNP6 Book on Unstructured Mesh Geometry: User’s Guide for MCNP 6.2.1,” LA-UR-18-27630, Los Alamos National Laboratory, Los Alamos, NM, USA (2018); doi:10.2172/1467189
  7. J. B. SPENCER, R. L. MARTZ and J. L. ALWIN, “Introduction to the MCNP6 Unstructured Mesh Geometry Capability,” LA-UR-18-24230, Los Alamos National Laboratory, Los Alamos, NM, USA (2018); doi:10.2172/1438161
  8. R. L. MARTZ and J. A. KULESZA, “Verification and Validation of Unstructured Mesh Tracking in the MCNP Code Version 6.2,” LA-UR-17-22660, Los Alamos National Laboratory, Los Alamos, NM, USA (2017); URL
  9. R. L. MARTZ, “Verification of the Multi-Mesh Capability for MCNP6’s Unstructured Mesh Feature,” LA-UR-16-23111, Los Alamos National Laboratory, Los Alamos, NM, USA (2016); URL
  10. R. L. MARTZ, “Flux Multiplier Capability for MCNP6’s Unstructured Mesh Feature,” LA-UR-16-22004, Los Alamos National Laboratory, Los Alamos, NM, USA (2016); URL
  11. K. ZIEB, R. L. MARTZ, “Evaluation of a Tentative Contiguous Mesh Particle Tracking Capability and Update of MCNP6 Performance Benchmarks with MCNP6’s Unstructured Mesh,” LA-UR-15-27000, Los Alamos National Laboratory, Los Alamos, NM, USA (2015); URL
  12. R. L. MARTZ, “The MCNP6 Book on Unstructured Mesh Geometry: Foundations,” LA-UR-12-25478 Rev. 1, Los Alamos National Laboratory, Los Alamos, NM, USA (2014); URL
  13. M. W. SHAVER, A. M. CASELLA, R. S. WITTMAN, B. S. MCDONALD, “Radiation Detection Computational Benchmark Scenarios,” PNNL-22794, Pacific Northwest National Laboratory, Richland, WA, USA (2013); doi:10.2172/1096696
  14. T. P. BURKE, B. C. KIEDROWSKI, R. L. MARTZ and W. R. MARTIN, “Reactor Physics Verification of the MCNP6 Unstructured Mesh Capability,” LA-UR-12-24277, Los Alamos National Laboratory, Los Alamos, NM, USA (2012); URL
    Also published as a Peer-reviewed Publication (see #52 below).
  15. T. P. BURKE, R. L. MARTZ, B. C. KIEDROWSKI and W. R. MARTIN, “Verification of Unstructured Mesh Capabilities in MCNP6 for Reactor Physics Problems,” LA-UR-12-24260, Los Alamos National Laboratory, Los Alamos, NM, USA (2012); URL
  16. M. W. SHAVER, E. A. MILLER, R. S. WITTMAN and B. S. MCDONALD, “Transport Test Problems for Hybrid Methods Development,” PNNL-21026, Pacific Northwest National Laboratory, Richland, WA, USA (2011); doi:10.2172/1035747
  17. M. W. SHAVER, “Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report,” PNNL-19795, Pacific Northwest National Laboratory, Richland, WA USA (2010); doi:10.2172/1015285
  18. D. S. LUCAS, H. D. GOUGAR, T. WAREING, G. FAILLA, J. MCGHEE, D. A. BARNETT and I. DAVIS, “Comparison of the 3-D Deterministic Neutron Transport Code Attila to Measured Data, MCNP and MCNPX for the Advanced Test Reactor,” INL/CON-05-00662, Idaho National Laboratory, Idaho Falls, ID, USA (2005).
    Also published as a Peer-reviewed Publication (see #36) below.
  19. D. S. LUCAS, H. D. GOUGAR, P. A. ROTH, T. WAREING, G. FAILLA, J. MCGHEE and A. BARNETT, “Applications of the 3-D Deterministic Transport Attila for Core Safety Analysis,” INEEL/CON-04/02354, Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID, USA (2004).
    Also published as a Peer-reviewed Publication (see #41) below.
  20. J. S. WARSA, T. A. WAREING and J. E. MOREL, “On the Degraded Effectiveness of Diffusion Synthetic Acceleration for Multidimensional SN Calculations in the Presence of Material Discontinuities,” LA-UR-02-6667, Los Alamos National Laboratory, Los Alamos, NM, USA (2003).
    Also published as a Peer-reviewed Publication (see #45 below).
  21. J. S. WARSA, T. A. WAREING and J. E. MOREL, “Krylov Iterative Methods Applied to Multidimensional SN Calculations in the Presence of Material Discontinuities,” LA-UR-02-6668, Los Alamos National Laboratory, Los Alamos, NM, USA (2003).
    Also published as a Peer-reviewed Publication (see #46 below).
  22. T. A. WAREING and J. M. MCGHEE, “Pericles and Attila Results for the C5G7 MOX Benchmark Problems,” LA-UR-02-0102, Los Alamos National Laboratory, Los Alamos, NM, USA (2002).
    Also published as a Peer-reviewed Publication (see #47 below).
  23. T. A. WAREING, J. E. MOREL and D. K. PARSONS, “A First Collision Source Method for ATTILA, an Unstructured Tetrahedral Mesh Discrete Ordinates Code,” LA-UR-98-1373, Los Alamos National Laboratory, Los Alamos, NM, USA (1998).
    Also published as a Peer-reviewed Publication (see #48 below).
  24. T. A. WAREING, D. K. PARSONS and S. PAUTZ, “A Reactor Pressure Vessel Dosimetry Calculation Using ATTILA, an Unstructured Tetrahedral Mesh Discrete Ordinates Code,” LA-UR-97-2268, Los Alamos National Laboratory, Los Alamos, NM, USA (1997).
    Also published as a Peer-reviewed Publication (see #49 below).

Peer-reviewed Publications

Attila and Attila4MC Usage

This subsection lists peer-reviewed publications that describe calculations performed with the use of Attila4MC and/or Attila. The verification, validation and use of Attila and/or Attila4MC is the primary topic of some, but not all, of these publications; every single publication in this subsection does present at least some results from Attila and/or Attila4MC.

  1. L. ZAVORKA and I. REMEC, “Neutron Dose Rate Calculation with the MCNP6 Hybrid Geometry Model of the Second Target Station,” Transactions of the American Nuclear Society, 124, 1, 680–683 (2021); doi:10.13182/T124-36275
  2. J. BROGAN, E. SOSNOVSKY and J. KULESZA, “Comparison of CADIS Implementations in Attila4MC and ADVANTG,” Transactions of the American Nuclear Society, 123, 1, 1185–1188 (2020); doi:10.13182/T123-33332
  3. N. H. WHITMAN and J. S. HADER, “Attila and MCNP6.2 Validation with the JASPER-IHX Benchmark for Sodium-Cooled Fast Reactor Shielding Applications,” Transactions of the American Nuclear Society, 121, 1, 1267–1270 (2019); doi:10.13182/T31226
  4. J. L. ALWIN, J. B. SPENCER and G. FAILLA, “Criticality Accident Alarm System Analysis Using MCNP6.2 Constructive Solid Geometry/Unstructured Mesh Hybrid,” Proc. ICNC, Paris, France, September 15–20, 2019.
    Also published as a Third-party Technical Report (see #5 above).
  5. M. LOVECKÝ, J. ZÁVORKA and J. VIMPEL, “VVER-1000 Fuel Assembly Model in CAD-based Unstructured Mesh for MCNP6,” Kerntechnik, 84, 4, 262–266 (2019); doi:10.3139/124.190041
  6. P. KANTH and P. V. SUBHASH, “ACTYS-ASG, Tool for Coupling ACTYS-1-GO with ATTILA,” Fusion Engineering and Design, 129, 196–201 (2018); doi:10.1016/j.fusengdes.2018.02.092
  7. J. A. KULESZA and R. L. MARTZ, “Evaluation of Pulsed Sphere Time-of-Flight and Neutron Attenuation Experimental Benchmarks Using MCNP6’s Unstructured Mesh Capabilities,” Nuclear Technology, 195, 1, 44–54 (2016); doi:10.13182/NT15-121
  8. J. A. KULESZA and R. L. MARTZ, “Evaluation of the Kobayashi Analytical Benchmark Using MCNP6’s Unstructured Mesh Capabilities,” Nuclear Technology, 195, 1, 55–70 (2016); doi:10.13182/NT15-122
  9. E. SOMASUNDARAM and T. S. PALMER, “Analysis of the LIFT Variance-Reduction Method Applied to Monte Carlo Radiation Transport Simulations of a Realistic Nonproliferation Test Problem,” Nuclear Technology, 193, 3, 391–403 (2016); doi:10.13182/NT15-43
  10. E. CASTANIER and D. KEROUANTON, “Evaluating the Gamma Dose Rate for the Liquid Waste Treatment Facility in Fukushima Site with Attila Radiation Transport Code,” Progress in Nuclear Science and Technology, 4, 1–4 (2014); doi:10.15669/pnst.4.1
  11. V. OLČOVCOVÁ, R. HALEY, L. MACFARLANE, B. RUS and M. GRIFFITHS, “Bulk Shielding for Laser Research Centre ELI Beamlines,” Progress in Nuclear Science and Technology, 4, 247–251 (2014); doi:10.15669/pnst.4.247
  12. I. M. DAVIS and R. L. MARTZ, “On the Benefits of Mesh Partnerships: Attila – MCNP6 Integration,” Transactions of the American Nuclear Society, 109, 1, 720–723 (2013); URL
  13. P. V. SUBHASH, R. FEDER, S. JAKHAR, S. THOMAS and D. AGGARWAL, “ITER Related Neutronics Calculations with ATTILA Computer Code,” Transactions of the American Nuclear Society, 109, 1, 1149–1150 (2013); URL
  14. R. FEDER, M. YOUSSEF and J. KLABACHA, “The Status of USITER Diagnostic Port Plug Neutronics Analysis Using Attila,” Transactions of the American Nuclear Society, 109, 1, 1159–1162 (2013); URL
  15. M. YOUSSEF, R. FEDER, P. BATISTONI, U. FISCHER, S. JAKHAR, C. KONNO, M. LOUGHLIN, R. VILLARI and Y. WU, “Benchmarking of the 3-D CAD-based Discrete Ordinates Code ‘ATTILA’ for Dose Rate Calculations Against Experiments and Monte Carlo Calculations,” Fusion Engineering and Design, 88, 11, 3033–3040 (2013); doi:10.1016/j.fusengdes.2013.07.010
  16. M. Z. YOUSSEF and R. FEDER, “Summary of the Up-to-Date 3-D Nuclear Analyses of ITER Diagnostics Generic Equatorial Port Plug (GEPP) Performed with the Attila Design Code,” Fusion Science and Technology, 64, 3, 571–581 (2013); doi:10.13182/FST64-571
  17. M. Z. YOUSSEF, R. FEDER, M. DAGHER, A. AOYAMA and M. DUCO, “Neutronics Analysis of the Divertor Interferometer Diagnostics Inside the Lower Port #8 Plug of ITER with ATTILA 3-D CAD-based FEM Code,” Fusion Science and Technology, 60, 2, 730–737 (2011); doi:10.13182/FST11-A12472
  18. A. T. AOYAMA, M. DAGHER, R. FEDER, M. DUCO and M. YOUSSEF, “Development of A‑LITE Model for Use in ATTILA Radiation Transport Finite Element Analysis of the ITER Lower Divertor Region,” Fusion Science and Technology, 60, 2, 830–834 (2011); doi:10.13182/FST11-A12489
  19. A. M. IBRAHIM, S. W. MOSHER, T. M. EVANS, D. E. PEPLOW, M. S. SAWAN, P. P. H. WILSON, J. C. WAGNER and T. HELTEMES, “ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic and CAD-based Monte Carlo Methods,” Nuclear Technology, 175, 1, 251–258 (2011); doi:10.13182/NT175-251
  20. C. KONNO, S. SATO, K. OCHIAI, M. WADA, S. OHNISHI, K. TAKAKURA and H. IIDA, “Attila Validation with Fusion Benchmark Experiments at JAEA/FNS,” Nuclear Technology, 168, 3, 743–746 (2009); doi:10.13182/NT09-A9299
  21. A. M. CASELLA, C. J. GESH and L. E. SMITH, “Use of Detector Response Functions and Deterministic Flux Calculations in Count Rate Predictions,” Transactions of the American Nuclear Society, 101, 1, 631–632 (2009); URL
  22. C. T. KELSEY IV and A. K. PRINJA, “Coupled Multigroup Proton/Neutron Cross Sections for Deterministic Transport,” Nuclear Technology, 168, 2, 257–263 (2009); doi:10.13182/NT09-A9191
  23. M. Z. YOUSSEF, R. FEDER, K. THOMPSON, I. DAVIS and G. FAILLA, “Benchmarking the Three-Dimensional CAD-Based Discrete Ordinates Code ‘ATTILA’ Using Integral Dose-Rate Experiments and Comparison to MCNP Results,” Fusion Science and Technology, 56, 2, 718–725 (2009); doi:10.13182/FST09-A8993
  24. R. PAMPIN, M. J. LOUGHLIN and M. J. WALSH, “Radiation Transport Analyses for Design Optimisation of the ITER Core LIDAR Diagnostic,” Fusion Science and Technology, 56, 2, 751–755 (2009); doi:10.13182/FST56-751
  25. R. E. FEDER and M. Z. YOUSSEF, “ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assessment Neutronics Analysis using the ATTILA Discrete Ordinates Code,” Proc. SOFE, San Diego, CA, USA, June 1–5, 2009; doi:10.1109/FUSION.2009.5226490
  26. W. ARTER and M. J. LOUGHLIN, “Radiation Transport Analyses for IFMIF Design by the Attila Software Using a Monte Carlo Source Model,” Fusion Engineering and Design, 84, 1, 89–96 (2009); doi:10.1016/j.fusengdes.2008.11.051
  27. M. Z. YOUSSEF, R. FEDER and I. M. DAVIS, “Neutronics Analysis of the International Thermonuclear Experimental Reactor (ITER) MCNP ‘Benchmark CAD Model’ with the ATTILA Discrete Ordinates Code,” Fusion Engineering and Design, 83, 10–12, 1661–1668 (2008); doi:10.1016/j.fusengdes.2008.05.040
  28. P. P. H. WILSON, R. FEDER, U. FISCHER, M. LOUGHLIN, L. PETRIZZI, Y. WU and M. YOUSSEF, “State-of-the-art 3-D Radiation Transport Methods for Fusion Energy Systems,” Fusion Engineering and Design, 83, 7–9, 824–833 (2008); doi:10.1016/j.fusengdes.2008.05.038
  29. L. E. SMITH, C. J. GESH, R. T. PAGH, E. A. MILLER, M. W. SHAVER, E. D. ASHBAKER, M. T. BATDORF, J. E. ELLIS, W. R. KAYE, R. J. MCCONN, G. H. MERIWETHER, J. J. RESSLER, A. B. VALSAN and T. A. WAREING, “Coupling Deterministic and Monte Carlo Transport Methods for the Simulation of Gamma Ray Spectroscopy Scenarios,” IEEE Transactions on Nuclear Science, 55, 5, 2598–2606 (2008); doi:10.1109/TNS.2008.2002819
  30. M. Z. YOUSSEF, P. BATISTONI, L. PATRIZZI, T. WAREING and I. M. DAVIS, “Comparing the Prediction of ‘Attila’ Code to the Experimental Data of Fusion Integral Experiments and to the Results of MCNP Code,” Fusion Science and Technology, 52, 4, 801–806 (2007); doi:10.13182/FST07-A1589
  31. R. FEDER, M. YOUSSEF, I. DAVIS, G. FAILLA and T. WAREING, “ITER Neutronics Analysis for the Design of Diagnostics and Port Plugs Using ATTILA Discrete Ordinates Software,” Proc. SOFE, Albuquerque, NM, USA, June 17–21, 2007; doi:10.1109/FUSION.2007.4337859
  32. M. Z. YOUSSEF, “Benchmarking the CAD-based ATTILA Discrete Ordinates Code with Experimental Data of Fusion Experiments and to the Results of MCNP Code in Simulating ITER,” Proc. ICENES, Istanbul, Turkey, June 3–8, 2007.
  33. T. WAREING, J. MCGHEE, A. BARNETT, G. FAILLA and I. DAVIS, “Capabilities of Attila for Radiation Protection and Shielding,” Transactions of the American Nuclear Society, 95, 1, 659–660 (2006); URL
  34. L. E. SMITH, C. J. GESH, R. T. PAGH, R. J. MCCONN, J. E. ELLIS, W. R. KAYE, G. H. MERIWETHER, E. MILLER, M. W. SHAVER, J. R. STARNER, A. B. VALSAN and T. A. WAREING, “Deterministic Transport Methods for the Simulation of Gamma-Ray Spectroscopy Scenarios,” Proc. NSS/MIC, San Diego, CA, USA, October 29–November 1, 2006; doi:10.1109/NSSMIC.2006.356224
  35. M. J. LOUGHLIN, T. WAREING, A. BARNETT, G. FAILLA and J. MCGHEE, “Comparison of Attila and MCNP for Fusion Applications,” Proc. M&C, Avignon, France, September 12–17, 2005.
  36. D. S. LUCAS, H. D. GOUGAR, T. WAREING, G. FAILLA, J. MCGHEE, D. A. BARNETT and I. DAVIS, “Comparison of the 3-D Deterministic Neutron Transport Code Attila to Measured Data, MCNP and MCNPX for the Advanced Test Reactor,” Proc. M&C, Avignon, France, September 12–17, 2005.
  37. J. A. GALBRAITH and L. E. GREENWADE, “Visualization of a Deterministic Radiation Transport Model Using Standard Visualization Tools,” Proc. CUG, Knoxville, TN, USA, May 17–21, 2004; URL
  38. J. S. WARSA, M. BENZI, T. A. WAREING and J. E. MOREL, “Preconditioning a Mixed Discontinuous Finite Element Method for Radiation Diffusion,” Numerical Linear Algebra with Applications, 11, 8–9, 795–811 (2004); doi:10.1002/nla.347
  39. J. S. WARSA, T. A. WAREING and J. E. MOREL, “Krylov Iterative Methods and the Degraded Effectiveness of Diffusion Synthetic Acceleration for Multidimensional SN Calculations in Problems with Material Discontinuities,” Nuclear Science and Engineering, 147, 3, 218–248 (2004); doi:10.13182/NSE02-14
  40. J. S. WARSA, T. A. WAREING, J. E. MOREL, J. M. MCGHEE and R. B. LEHOUCQ, “Krylov Subspace Iterations for Deterministic k-Eigenvalue Calculations,” Nuclear Science and Engineering, 147, 1, 26–42 (2004); doi:10.13182/NSE04-1
  41. D. S. LUCAS, H. D. GOUGAR, P. A. ROTH, T. WAREING, G. FAILLA, J. MCGHEE and A. BARNETT, “Applications of the 3-D Deterministic Transport Attila for Core Safety Analysis,” Proc. ANES, Miami Beach, FL, USA, October 3–6, 2004.
  42. R. C. SINGLETERRY JR., B. D. JOHNS, K. Y. FAN, F. M. CHEATWOOD, G. D. QUALLS, T. A. WAREING, J. MCGHEE, S. PAUTZ, A. K. PRINJA, F. GLEICHER, G. FAILLA, J. SOBIESZCZANSKI-SOBIESKI and J. W. WILSON, “Development of Collaborative Engineering Environments for Spacecraft Design,” AIP Conference Proceedings, 654, 1, 907–916 (2003); doi:10.1063/1.1541384
  43. J. S. WARSA, M. BENZI, T. A. WAREING and J. E. MOREL, “Two-level Preconditioning of a Discontinuous Galerkin Method for Radiation Diffusion,” Numerical Mathematics and Advanced Applications, 967–977 (2003); doi:10.1007/978-88-470-2089-4_88
  44. J. S. WARSA, T. A. WAREING and J. E. MOREL, “Fully Consistent Diffusion Synthetic Acceleration of Linear Discontinuous SN Transport Discretizations on Unstructured Tetrahedral Meshes,” Nuclear Science and Engineering, 141, 3, 236–251 (2002); doi:10.13182/NSE141-236
  45. J. S. WARSA, T. A. WAREING and J. E. MOREL, “On the Degraded Effectiveness of Diffusion Synthetic Acceleration for Multidimensional SN Calculations in the Presence of Material Discontinuities,” Proc. M&C, Gatlinburg, TN, USA, April 6–11, 2003.
    Also published as a Third-party Technical Report (see #20 above).
  46. J. S. WARSA, T. A. WAREING and J. E. MOREL, “Krylov Iterative Methods Applied to Multidimensional SN Calculations in the Presence of Material Discontinuities,” Proc. M&C, Gatlinburg, TN, USA, April 6–11, 2003.
    Also published as a Third-party Technical Report (see #21 above).
  47. T. A. WAREING and J. M. MCGHEE, “Pericles and Attila Results for the C5G7 MOX Benchmark Problems,” Proc. PHYSOR, Seoul, South Korea, October 7–10, 2002.
    Also published as a Third-party Technical Report (see #22 above).
  48. T. A. WAREING, J. E. MOREL and D. K. PARSONS, “A First Collision Source Method for ATTILA, an Unstructured Tetrahedral Mesh Discrete Ordinates Code,” Proc. ANS RPSD Topical Meeting, Nashville, TN, USA, April 19–23, 1998.
    Also published as a Third-party Technical Report (see #23 above).
  49. T. A. WAREING, D. K. PARSONS and S. PAUTZ, “A Reactor Pressure Vessel Dosimetry Calculation Using ATTILA, an Unstructured Tetrahedral Mesh Discrete Ordinates Code,” Proc. M&C+SNA, Saratoga Springs, NY, USA, October 5–9, 1997.
    Also published as a Third-party Technical Report (see #24 above).
  50. T. A. WAREING, J. M. MCGHEE and J. E. MOREL, “ATTILA: A Three-Dimensional, Unstructured Tetrahedral Mesh Discrete Ordinates Transport Code,” Transactions of the American Nuclear Society, 75, 146–147 (1996).

Radiation Transport on Unstructured Mesh

This subsection lists peer-reviewed publications about the general topic of radiation transport (primarily Monte Carlo) simulations on unstructured meshes. These publications do not present any results from Attila or Attila4MC, but may be of interest to engineers more familiar with radiation transport on Constructive Solid Geometry (CSG).

  1. R. L. MARTZ and K. M. MARSHALL, “A Notable Comparison of Computational Geometries in MCNP6 Calculations,” Nuclear Technology, 184, 2, 239–248 (2013); doi:10.13182/NT13-A22319
  2. T. P. BURKE, B. C. KIEDROWSKI, R. L. MARTZ and W. R. MARTIN, “Reactor Physics Verification of the MCNP6 Unstructured Mesh Capability,” Proc. M&C, Sun Valley, ID, USA, May 5–9, 2013.
  3. T. A. WAREING, J. M. MCGHEE, J. E. MOREL and S. D. PAUTZ, “Discontinuous Finite Element SN Methods on Three-Dimensional Unstructured Grids,” Nuclear Science and Engineering, 138, 3, 256–268 (2001); doi:10.13182/NSE138-256