Effect of group averaging of constants in the solution of the neutron transport equation by the Monte Carlo method

1977 ◽  
Vol 20 (5) ◽  
pp. 664-666
Author(s):  
G. Sh. Pekarskii ◽  
Yu. Ya. Katsman ◽  
G. A. Kucher
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Transport Equation ◽  
Neutron Transport ◽  
Neutron Transport Equation ◽  
The Monte Carlo Method ◽  
Group Averaging

Monte Carlo Integration of the Adjoint Neutron Transport Equation

1969 ◽  
Vol 37 (3) ◽  
pp. 410-422 ◽  
Author(s):  
Bo Eriksson ◽  
Claes Johansson ◽  
Martin Leimdorfer ◽  
M. H. Kalos
Keyword(s):  
Monte Carlo ◽  
Transport Equation ◽  
Neutron Transport ◽  
Monte Carlo Integration ◽  
Neutron Transport Equation

scholarly journals Solution methods of neutron transport equation in nuclear reactors

2013 ◽  
Vol 14 (2) ◽  
pp. 59
Author(s):  
Mohamad Ali Shafii
Keyword(s):  
Monte Carlo ◽  
Transport Equation ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Neutron Transport ◽  
Collision Probability ◽  
Computer Memory ◽  
Neutron Transport Equation ◽  
Solution Methods ◽  
Transport Approximation

A few numerical methods that usually used to solve neutron transport equation in nuclear reactor are SN dan PN method, Monte Carlo, Collision Probability and Methods of Characteristics . First two methods have been developed using diffusion approach, and last three methods suitable are applicated for transport approximation. Those of three methods have important role in the desain of nuclear reactors. In addition to follow the development of advanced reactor designs, the three methods were chosen because they do not use diffusion approach these are more accurate methods, as well as less need considerable computer memory. Of all the existing methods, the CP method has several advantages among the others. Keywords : Neutron transport, SN, PN, CP, MOC, MC

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