In cooperation with the Iranian Nuclear Society

Time and Space Dependent Neutronic Calculations Using TDMC Monte Carlo Code

Document Type : Research Paper

Authors

Abstract
Time-dependent behavior of fission reactors is simulated using Monte Carlo method and a code named TDMC is developed for neutron parameters calculations. Parameters such as reactivity, neutron life time, space distribution of flux, and power with several groups of delayed neutrons are calculable by the code. Material composition and system boundaries may be changed as time-dependent in the code. The results which have obtained with the code are in good agreement with the benchmark problems results.

Highlights

  1. 1.     M. Shayesteh, M. Shahriari, G. Raisali, “Simulation of time dependent neutron transport in fission reactors using Monte-Carlo method,” Journal of Nuclear Science and Technology, 39, 1-8 (2007).

 

  1. 2.     N.S. Garis, I. Pazsit, D.C. Sahni, “Modeling of a vibrating reactor boundary and calculation of the induced neutron noise,” Annals of Nuclear Energy, 23, 1197-1208 (1996).

 

  1. 3.     V. Arzhanov, “Multi-group theory of neutron noise induced by vibrating boundaries,” Annals of Nuclear Energy, 29, 2143-2158 (2002).

 

  1. 4.     I. Pazsit and V. Arzhanov, “Linear reactor kinetics and neutron noise in systems with fluctuating boundaries,” Annals of Nuclear Energy, 27, 1385-1398 (2000).

 

  1. 5.     Weston M. Stacey, “Nuclear reactor physics,” John Wiley & Sons, New York, Chapter, 2 (2001).

 

  1. 6.     J.J. Duderstadt and L.J. Hamilton, “Nuclear reactor analysis,” John Wiley & Sons, New York, Chapter, 2 (1976).

 

  1. 7.     A.F. Henry, “Nuclear reactor analysis,” MIT Press, Cambridge, Massachusetts, Chapter, 7 (1975).

 

  1. 8.     T.R. Hill and W.H. Reed, “TIMEX: a time-dependent explicit discrete ordinates program for the solution of multigroup transport equation with delayed neutron,” LA-6201-MS, Los Alamos Scientific Laboratory (1976).

 

  1. 9.     S. Goluoglu and H.L. Dodds, “A time-dependent three-dimensional neutron transport methodology,” Nucl. Sci. & Eng, 139, 248-261 (2001).

 

10. Z.A. Akcasu, G.S. Lellouche, S. Gerald, L.M. Shotkin, “Mathematical methods in nuclear reactor dynamics,” ACADEMIC Press, INC, U.S. (1971).

Keywords


  1. 1.     M. Shayesteh, M. Shahriari, G. Raisali, “Simulation of time dependent neutron transport in fission reactors using Monte-Carlo method,” Journal of Nuclear Science and Technology, 39, 1-8 (2007).

 

  1. 2.     N.S. Garis, I. Pazsit, D.C. Sahni, “Modeling of a vibrating reactor boundary and calculation of the induced neutron noise,” Annals of Nuclear Energy, 23, 1197-1208 (1996).

 

  1. 3.     V. Arzhanov, “Multi-group theory of neutron noise induced by vibrating boundaries,” Annals of Nuclear Energy, 29, 2143-2158 (2002).

 

  1. 4.     I. Pazsit and V. Arzhanov, “Linear reactor kinetics and neutron noise in systems with fluctuating boundaries,” Annals of Nuclear Energy, 27, 1385-1398 (2000).

 

  1. 5.     Weston M. Stacey, “Nuclear reactor physics,” John Wiley & Sons, New York, Chapter, 2 (2001).

 

  1. 6.     J.J. Duderstadt and L.J. Hamilton, “Nuclear reactor analysis,” John Wiley & Sons, New York, Chapter, 2 (1976).

 

  1. 7.     A.F. Henry, “Nuclear reactor analysis,” MIT Press, Cambridge, Massachusetts, Chapter, 7 (1975).

 

  1. 8.     T.R. Hill and W.H. Reed, “TIMEX: a time-dependent explicit discrete ordinates program for the solution of multigroup transport equation with delayed neutron,” LA-6201-MS, Los Alamos Scientific Laboratory (1976).

 

  1. 9.     S. Goluoglu and H.L. Dodds, “A time-dependent three-dimensional neutron transport methodology,” Nucl. Sci. & Eng, 139, 248-261 (2001).

 

10. Z.A. Akcasu, G.S. Lellouche, S. Gerald, L.M. Shotkin, “Mathematical methods in nuclear reactor dynamics,” ACADEMIC Press, INC, U.S. (1971).