Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Simulation of Time Dependent Neutron Transport in Fission Reactors Using Monte-Carlo Method

Document Type : Research Paper

Authors

M Shayesteh
M Shahriari
G Raisali
Abstract
In this paper, time dependent neutron transport in fissionable media is simulated by Monte Carlo method, and the neutronic parameters are estimated. In this article, the effective multiplication factor, neutron lifetime, and flux distribution in steady state condition are calculated. The comparison of the results obtained by this method, with those of the experimental measurements and the other calculations have shown that they are in very good agreement.

Highlights

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

 

  1. 2.    H. Rief and H. Kschwendt, “Reactor analysis by Monte Carlo,” Nucl.Sci. & Eng. 30, 395-418 (1967).

 

  1. 3.    “MCNP4C, Monte Carlo N-Particle Code System,” Los Alamos National Laboratory, Lose Alamos, New Mexico (2000).

 

  1. 4.     H. Kahn, “Application of Monte Carlo,” AECU-3259, Rand Corporation, Santa Monica (1954).

 

  1. 5.    T. Asaoka, “Neutron transport in a spherical reactor, a study in the application of the jN approximation of the Multiple Collision Method,” EUR  2627. e, Euratom-Ispra (1966).

 

  1. 6.    R.E. Peterson and G.A. NEWBY, “An unreflected U-235 critical assembly,” Nucl. Sci. & Eng. 1,112 (1965).

 

  1. 7.    R.H. White, “Topsy, a remotely controlled critical assembly machine,”  Nucl.Sci. & Eng.1 ,53 (1965).

 

  1. 8.     G.E. Hansen and W.H. Roach, “Six and sixteen group cross sections for fast and intermediate critical assemblies,” LAMS-2543, Los Alamos Scientific Laboratory   (1961).

 

 

 

 

 

 


 

 

 

 

 

Keywords

Fissionable Systems
Neutronic Parameters
Monte Carlo Method
Criticality Calculations
Neutron Lifetime
  1. 1.    S. Goluoglu and H.L. Dodds, “A time-dependent three-dimensional neutron transport methodology,” Nucl.Sci. & Eng. 139, 248-261 (2001).

 

  1. 2.    H. Rief and H. Kschwendt, “Reactor analysis by Monte Carlo,” Nucl.Sci. & Eng. 30, 395-418 (1967).

 

  1. 3.    “MCNP4C, Monte Carlo N-Particle Code System,” Los Alamos National Laboratory, Lose Alamos, New Mexico (2000).

 

  1. 4.     H. Kahn, “Application of Monte Carlo,” AECU-3259, Rand Corporation, Santa Monica (1954).

 

  1. 5.    T. Asaoka, “Neutron transport in a spherical reactor, a study in the application of the jN approximation of the Multiple Collision Method,” EUR  2627. e, Euratom-Ispra (1966).

 

  1. 6.    R.E. Peterson and G.A. NEWBY, “An unreflected U-235 critical assembly,” Nucl. Sci. & Eng. 1,112 (1965).

 

  1. 7.    R.H. White, “Topsy, a remotely controlled critical assembly machine,”  Nucl.Sci. & Eng.1 ,53 (1965).

 

  1. 8.     G.E. Hansen and W.H. Roach, “Six and sixteen group cross sections for fast and intermediate critical assemblies,” LAMS-2543, Los Alamos Scientific Laboratory   (1961).

 

 

 

 

 

 


 

 

 

 

 

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