Difference between revisions of "Delta- and surface-tracking"

From Serpent Wiki
Jump to: navigation, search
Line 1: Line 1:
This a brief description on the delta-tracking based transport routine used in Serpent. The original delta-tracking algorithm was introduced by Woodcock in 1965,<ref>Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. ''"Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry."'' ANL-7050, Argonne National Laboratory, 1965.</ref> and a mathematical verification was derived by Coleman in 1968.<ref>Coleman, W. A. ''"Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems."'' Nucl. Sci. Eng., '''31''' (1968) 76–81.</ref> The method is also described in a text book by Lux and Koblinger,<ref>Lux, I. and Koblinger, L. ''"Monte Carlo Particle Transport Methods: Neutron and Photon Calculations."'' CRC Press, Inc. (1991).</ref>.
+
This a brief description on the delta-tracking based transport routine used in Serpent. The original delta-tracking algorithm was introduced by Woodcock in 1965,<ref>Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. ''"Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry."'' ANL-7050, Argonne National Laboratory, 1965.</ref> and a mathematical verification was derived by Coleman in 1968.<ref>Coleman, W. A. ''"Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems."'' Nucl. Sci. Eng., '''31''' (1968) 76–81.</ref> The method is well described in a text book by Lux and Koblinger,<ref>Lux, I. and Koblinger, L. ''"Monte Carlo Particle Transport Methods: Neutron and Photon Calculations."'' CRC Press, Inc. (1991).</ref> and the basic routine used in Serpent in an article in Annals of Nuclear Energy from 2010.<ref>Leppänen, J. ''"Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code."'' Ann. Nucl. Energy '''37''' (2010) 715–722.</ref>.
  
  

Revision as of 16:05, 19 November 2015

This a brief description on the delta-tracking based transport routine used in Serpent. The original delta-tracking algorithm was introduced by Woodcock in 1965,[1] and a mathematical verification was derived by Coleman in 1968.[2] The method is well described in a text book by Lux and Koblinger,[3] and the basic routine used in Serpent in an article in Annals of Nuclear Energy from 2010.[4].


Transport algorithm in Monte Carlo simulation

Surface- and delta-tracking

Hybrid method used in Serpent

Advantages and limitations

References

  1. ^ Woodcock, E. R., Murphy, T., Hemmings, P. J., and Longworth, T. C. "Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry." ANL-7050, Argonne National Laboratory, 1965.
  2. ^ Coleman, W. A. "Mathematical verification of a certain Monte Carlo sampling technique and applications of the technique to radiation transport problems." Nucl. Sci. Eng., 31 (1968) 76–81.
  3. ^ Lux, I. and Koblinger, L. "Monte Carlo Particle Transport Methods: Neutron and Photon Calculations." CRC Press, Inc. (1991).
  4. ^ Leppänen, J. "Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code." Ann. Nucl. Energy 37 (2010) 715–722.