scholarly journals MCNA: A COMPUTER PROGRAM TO SOLVE THE ADJOINT NEUTRON TRANSPORT EQUATION BY COUPLED SAMPLING WITH THE MONTE CARLO METHOD.

1970 ◽  
Author(s):  
L.L. Carter
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Computer Program ◽  
Transport Equation ◽  
Neutron Transport ◽  
Neutron Transport Equation ◽  
The Monte Carlo Method

Clustering of Disfluencies in the Speech of Stuttering and Nonstuttering Preschool Children

1988 ◽  
Vol 31 (2) ◽  
pp. 228-233 ◽  
Author(s):  
Carol P. Hubbard ◽  
Ehud Yairi
Keyword(s):  
Monte Carlo ◽  
Preschool Children ◽  
Monte Carlo Method ◽  
Computer Program ◽  
Cluster Formation ◽  
Simulation Models ◽  
Control Subjects ◽  
The Monte Carlo Method

Cluster formation in speech disfluencies of 15 preschool stuttering children and an equal number of nonstuttering control subjects was studied and compared. Clustering was defined as the occurrence of two or more disfluencies on the same or adjacent words. A computer program, based on the Monte Carlo method, was used to generate sets of expected numbers of single disfluencies and disfluencies in various cluster sizes according to simulation models. Results indicate that disfluencies occurred in clusters more often than could have been expected by chance for both groups. The proportions of clustered disfluencies, as well as the size of clusters, in the speech of the stutterers were significantly greater than those of the nonstuttering subjects.

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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