MCNP

MCNP-A General Monte Carlo N-Particle Transport Code. Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes. It is developed by Los Alamos National Laboratory since at least 1957 with several further major improvements. It is distributed within the United States by the Radiation Safety Information Computational Center in Oak Ridge, TN and internationally by the Nuclear Energy Agency in Paris, France. It is used primarily for the simulation of nuclear processes, such as fission, but has the capability to simulate particle interactions involving neutrons, photons, and electrons. ”Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning.”


References in zbMATH (referenced in 38 articles )

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  1. Seiki Ohnishi: Gxsview: Geometry and cross section viewer for calculating radiation transport (2021) not zbMATH
  2. Favetti, R.; Chiovaro, P.; Di Maio, P. A.; Spagnuolo, G. A.: Validation of multi-physics integrated procedure for the HCPB breeding blanket (2020)
  3. Hamada, Yasser Mohamed: Solution of a new model of fractional telegraph point reactor kinetics using differential transformation method (2020)
  4. Li, Xinge; Xu, Haibo; Zheng, Na; Jia, Qinggang; Gu, Tongxiang; Wei, Suhua: Uncertainty quantification of density reconstruction using MCMC method in high-energy X-ray radiography (2020)
  5. Stewart Boogert, Andrey Abramov, Laurence Nevay, William Shields, Stuart Walker: PYG4OMETRY: a Python library for the creation of Monte Carlo radiation transport physical geometries (2020) arXiv
  6. Pichard, Teddy; Brull, Stéphane; Dubroca, Bruno: A numerical approach for a system of transport equations in the field of radiotherapy (2019)
  7. Valentin Niess, Anne Barnoud, Cristina Cârloganu, Olivier Martineau-Huynh: TURTLE: A C library for an optimistic stepping through a topography (2019) arXiv
  8. Lam, Adam Q.; Walsh, Jonathan A.; Palmer, Todd S.: Demonstration of multigroup multiband cross Section generation in Monte Carlo simulations (2018)
  9. Roshani, Gholam Hossein; Karami, Alimohammad; Nazemi, Ehsan; Shama, Farzin: Volume fraction determination of the annular three-phase flow of gas-oil-water using adaptive neuro-fuzzy inference system (2018)
  10. Zhukovskiĭ, M. E.; Uskov, R. V.; Savenkov, E. B.; Alekseev, M. V.; Markov, M. B.; Voronin, F. N.: The model of the radiation transport in the matter of heterogeneous materials of the porous type (2018)
  11. Barcellos, L. F. F. Chaves; Bodmann, B. E. J.; Leite, S. Q. Bogado; Vilhena, M. T.: On a continuous energy Monte Carlo simulator for neutron transport: optimisation with fission, intermediate and thermal distributions (2017)
  12. Garcia, R. D. M.; Vieira, W. J.: Application of 1D models to particle transport in a duct of rectangular cross Section (2017)
  13. Howard, Marylesa; Fowler, Michael; Luttman, Aaron; Mitchell, Stephen E.; Hock, Margaret C.: Bayesian Abel inversion in quantitative X-ray radiography (2016)
  14. McCulloch, Richard; Bindra, Hitesh: Coupled radiative and conjugate heat transfer in participating media using lattice Boltzmann methods (2016)
  15. Pandya, Tara M.; Johnson, Seth R.; Evans, Thomas M.; Davidson, Gregory G.; Hamilton, Steven P.; Godfrey, Andrew T.: Implementation, capabilities, and benchmarking of shift, a massively parallel Monte Carlo radiation transport code (2016)
  16. Zhang, Dingkang; Rahnema, Farzad: The adjoint coarse mesh transport (COMET) method and reciprocity relation of response coefficients (2016)
  17. Choi, Sooyoung; Smith, Kord; Lee, Hyun Chul; Lee, Deokjung: Impact of inflow transport approximation on light water reactor analysis (2015)
  18. Udagedara, Indika; Helenbrook, Brian; Luttman, Aaron; Mitchell, Stephen E.: Reduced order modeling for accelerated Monte Carlo simulations in radiation transport (2015)
  19. Bernal, A.; Abarca, A.; Barrachina, T.; Miró, R.: Methodology to resolve the transport equation with the discrete ordinates code TORT into the IPEN/MB-01 reactor (2014)
  20. Tickner, James: Arbitrary perturbations in Monte Carlo neutral-particle transport (2014)

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