EDP Sciences logo
Submit your paper
Search
Menu
All issues Volume 10 (2024) EPJ Nuclear Sci. Technol., 10 (2024) 14 References
Issue
EPJ Nuclear Sci. Technol.
Volume 10, 2024
Status and advances of Monte Carlo codes for particle transport simulation
Article Number 14
Number of page(s) 10
DOI https://doi.org/10.1051/epjn/2024014
Published online 05 November 2024
  1. Q.M. He, Q. Zheng, J. Li, H.C Wu, W. Shen, L.Z. Cao, Z.Y. Liu, H.L. Xu, NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems, Ann. Nucl. Energy 151, 107978 (2021) [CrossRef] [Google Scholar]
  2. L.F. Xu, L.Z. Cao, Y.Q. Zheng, H.C. Wu, Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry, Prog. Nucl. Energy 94, 1 (2017) [CrossRef] [Google Scholar]
  3. K.B. Bekar, T.M. Evans, MCNP-BRL: a Linkage Between MCNP and CAD Geometry, Trans. Am. Nucl. Soc. 101, 623 (2009) [Google Scholar]
  4. J. Tabary, A. Glière, Coupling Photon Monte Carlo Simulation and CAD Software, Application to X-ray Nondestructive Evaluation, in Proceedings of the Monte Carlo 2000 Conference, Lisbon, (Springer, Berlin, Heidelberg, 2000), p. 461 [Google Scholar]
  5. P.P.H. Wilson, T.J. Tautges, J.A. Kraftcheck, B.M. Smith, D.L. Henderson, Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis, Fusion Eng. Des. 85, 1759 (2010) [CrossRef] [Google Scholar]
  6. J. Leppänen, Methodology, applications and Performance of the CAD-Based Geometry Type in the Serpent 2 Monte Carlo Code, Ann. Nucl. Energy 176, 109259 (2022) [CrossRef] [Google Scholar]
  7. Y.C Wu, FDS Team, CAD-Based Interface Programs for Fusion Neutron Transport Simulation, Fusion Eng. Des. 84, 7 (2009) [Google Scholar]
  8. F. Moro, U. Fischer, L. Lu, P. Pereslavtsev, S. Podda, R. Villari, The McCad Code for the automatic generation of MCNP 3-D models: applications in fusion neutronics, IEEE Trans. Plasma Sci. 42, 4 (2014) [Google Scholar]
  9. S. Sato, H. Nashif, F. Masuda, H. Morota, H. Iida, C. Konno, Progress of conversion system from CAD data to MCNP geometry data in Japan, Fusion Eng. Des. 85, 7 (2010) [Google Scholar]
  10. H. Du, Y.T. Luo, C. Han, L. Lu, Y. Yan, Y. Sun, Y. Chen, S. Liu, Development of an assistant program for CAD-to-cosRMC modelling, Fusion Eng. Des. 157, 109259 (2020) [Google Scholar]
  11. R.L. Martz, MCNP6 unstructured mesh initial validation and performance results, Nucl. Technol. 180, 3 (2012) [Google Scholar]
  12. H.L. Shu, L.Z. Cao, Q.M. He, Q. Zheng, T. Dai, Study on unstructured mesh–based Monte Carlo/deterministic coupled particle transport calculation method, Nucl. Sci. Eng. 2, 1 (2024) [Google Scholar]
  13. J. Stepanek, T. Auerbach, W. Hälg, Calculation of Four Thermal Reactor Benchmark Problems In X-Y Geometry, EIR-Bericht Nr. 464, Eidg. (Institut für Reaktorforschung Würenlingen, Schweiz, 1982) [Google Scholar]
  14. J.C. Wagner, A. Haghighat, Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function, Nucl. Sci. Eng. 128, 186 (1998) [CrossRef] [Google Scholar]
  15. A. Haghighat, J.C. Wagner, Monte Carlo variance reduction with deterministic importance functions, Prog. Nucl. Energy 42, 25 (2003) [CrossRef] [Google Scholar]
  16. J.C. Wagner, E.D. Blakeman, D.E. Peplow, Forward-weighted cadis method for variance reduction of Monte Carlo calculations of distributions and multiple localized quantities on CD-ROM, American Nuclear Society International Conference on Mathematics, Computational Methods & Reactor Physics, (Saratoga Springs, New York, 2009) [Google Scholar]
  17. Q. Zheng, W. Shen, Q.M. He, J. Li, L.Z. Cao, H.C. Wu, High-efficiency simulation of VENUS-3 neutron-shielding problem with an automatic and enhanced hybrid Monte-Carlo-deterministic method, Ann. Nucl. Energy 153, 108039 (2021) [CrossRef] [Google Scholar]
  18. Q.M. He, Z.P. Huang, L.Z. Cao, H.C. Wu, The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications, Nucl. Eng. Technol. 56, 2748 (2024) [CrossRef] [Google Scholar]
  19. IAEA, Advances in Boron Neutron Capture Therapy (IAEA, Vienna, 2023) [Google Scholar]
  20. W. Sauerwein, A. Wittig, R. Moss, Y. Nakagawa, Neutron Capture Therapy, Principles and Applications (Springer Science & Business Media, New York, 2012) [CrossRef] [Google Scholar]
  21. J. Chen, Y.C. Teng, W.B. Zhong H.B. Yang, Q. Hong, Y.H. Liu, Development of Monte Carlo based treatment planning system for BNCT, J. Phys. Conf. Ser. 2313, 012012 (2022) [CrossRef] [Google Scholar]
  22. G. Li, Monte Carlo simulation method and code development for Boron Neutron Capture Therapy, Master thesis, China Academy of Engineering Physics, China, 2005 [Google Scholar]
  23. P.K. Romano, B. Forget, Reducing parallel communication in Monte Carlo simulations via batch statistics. Trans. Am. Nucl. Soc. 107, 519 (2012) [Google Scholar]
  24. J.T. Goorley, W.S. Kiger, R.G. Zamenhof, Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models, Med. Phys. 29, 145 (2002) [CrossRef] [Google Scholar]
  25. T. Furuta, T. Sato, Medical application of particle and heavy ion transport code system PHITS, Radiol. Phys. Technol. 14, 215 (2021) [CrossRef] [Google Scholar]
  26. A. Rouchon, A. Zoia, R. Sanchez, A new Monte Carlo method for neutron noise calculations in the frequency domain, Ann. Nucl. Energy 102, 465 (2016) [Google Scholar]
  27. K.F. Raskach, V.V. Korobeinikov, Effective algorithm for calculation of a subcritical reactor with an external source, At. Energy 85, 911 (1998) [CrossRef] [Google Scholar]
  28. Q. Zheng, H.C. Wu, Y.Z. Li, L.Z. Cao, M.T. He, Coupled stochastic-deterministic method for accelerator-driven subcritical system transient analysis, High Laser Part. Beams 30.1, 016001-1 (2018) [Google Scholar]
  29. J.L. Huang, L.Z. Cao, Q.M. He, C.H Wan, H.C Wu, Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX, Prog. Nucl. Energy 160, 104666 (2023) [CrossRef] [Google Scholar]
  30. J.L. Huang, L.Z. Cao, Q.M. He, C.H Wan, W. Shen, H.C Wu, Development and enhancement of generalized sensitivity analysis capability of continuous-energy nuclear data in NECP-MCX, in Proceedings of M &C 2023, (Ontario, Canada, 2023) [Google Scholar]
  31. J.L. Huang, L.Z. Cao, Q.M. He, C.H Wan, H.C Wu, Development of sensitivity calculation capability of Legendre moments of scattering angular distributions in NECP-MCX, submit for SNA + MC 2024, Paris, France (unpublished) [Google Scholar]
  32. J.L Huang L.Z. Cao, Q.M. He, J. Li, W. Shen, Sensitivity analysis of continuous-energy nuclear data and its application in AP1000, At. Energy Sci. Technol. 56, 53 (2022) [Google Scholar]
  33. K Huang, H.C. Wu, L.Z. Cao, Y.Z. Li, W Shen, Improvements to the transmutation trajectory analysis of depletion evaluation, Ann. Nucl. Energy 87, 637 (2016) [CrossRef] [Google Scholar]
  34. Q.M. He, J Li, H.L. Shu, L.Z. Cao, H.C. Wu, W Shen, Particle-transport/depletion/activation/source-term coupling analysis for CFETR with NECP-MCX, Fusion Eng. Des. 188, 113399 (2023) [CrossRef] [Google Scholar]
  35. E.T. Cheng, R.A. Forrest, A.B. Pashchenko, Report on the second international activation calculation benchmark comparison study INDC(NDS)-300, IAEA, 1994 [Google Scholar]
  36. P. Batistoni, M. Angelone, L. Petrizzi, M. Pillon, Experimental validation of shut down dose rates calculations inside ITER cryostat, Fusion Eng. Des. 58, 613 (2001) [CrossRef] [Google Scholar]
  37. Z.Y. Zhang, Z.X. Wu, Y.L Sun, F. Li, Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM, Nucl. Eng. Des. 236, 485 (2006) [CrossRef] [Google Scholar]
  38. S. Qin, Y.Z. Li, Q.M. He, L.Z. Cao, Y.P. Wang, Y.X. Wu, H.C. Wu, Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX, Nucl. Eng. Technol. 55, 3450 (2023) [CrossRef] [Google Scholar]
  39. B. Widom, Random sequential addition of hard spheres to a volume, J. Chem. Phys. 4410, 3888 (1966) [CrossRef] [Google Scholar]
  40. W.S. Jodrey, E.M. Tory, Computer simulation of close random packing of equal spheres, Phys. Rev. A 324, 2347 (1985) [CrossRef] [Google Scholar]
  41. Open CASCADE official document, https://www.opencascade.com [Google Scholar]
  42. FreeCAD official document, https://wiki.freecad.org [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.