1. Not finding help here? Sign up for a free 30min tutor trial with Chegg Tutors
    Dismiss Notice
Dismiss Notice
Join Physics Forums Today!
The friendliest, high quality science and math community on the planet! Everyone who loves science is here!

MonteCarlo neutron transport

  1. Jan 16, 2007 #1
    Can anyone hepl me with this?I need some web resource,to start learning from scratch.
     
  2. jcsd
  3. Jan 16, 2007 #2

    Astronuc

    User Avatar

    Staff: Mentor

    Try these to get started.

    Introduction to Numerical Simulations in Radiation Transport
    http://iron.nuc.berkeley.edu/~bdwirth/Public/NE155/ne155.html
    Notes in pdf
    http://iron.nuc.berkeley.edu/~bdwirth/Public/NE155/schedule.html
    Several files are large.

    Brief history of MCNP - Monte Carlo Neutron-Photon
    http://library.lanl.gov/cgi-bin/getfile?00418730.pdf

    LANL paper - A Monte Carlo Code for Particle Transport
    http://www.fas.org/sgp/othergov/doe/lanl/pubs/00326727.pdf

    Another historical perspective on MC -
    http://library.lanl.gov/cgi-bin/getfile?00326867.pdf

    MCNP site
    http://mcnp-green.lanl.gov/index.html
    http://mcnp-green.lanl.gov/v_r_refs.html
     
  4. Jan 16, 2007 #3

    Morbius

    User Avatar
    Science Advisor

    Milentije,

    A very good book on Monte Carlo is by Spanier and Gelbard;
    "Monte Carlo Principles and Neutron Transport Problems"

    There's also another short text by Carter and Cashwell.

    Dr. Gregory Greenman
    Physicist
     
  5. Jan 18, 2007 #4
    Thanks Astronuc and Morbius,I have found the recources very usefull.
     
  6. Apr 30, 2011 #5
    Hello friends, I am doing simple mc simulation for neutron transport.
    The principle of random simulation is L=-(1/C)*ln(u), where u is a random number from the uniform distribution [0,1), and c is the total cross section (absorbed + scattered). Could you explain me what is the meaning of u, and how can I use it in my simulation?.
    I wrote a simple code in c, which I have to parallel it in MPI:

    #include "mpi.h"
    #include <math.h>
    #include <time.h>
    #include <stdio.h>
    #include <stdlib.h>
    #include <errno.h>
    #include <stdbool.h>
    #define PI 3.14159265
    int main (int argc, char *argv[])
    {
    /* Simple "srand()" seed: just use "time()" */
    unsigned int iseed = (unsigned int)time(NULL);
    srand (iseed);

    /*c = mean distance between neutron/atom interaction*/
    /*cs = scattering component of c*/
    /*cc = absorbing component of c*/
    float c,cs,cc; /*mean distance between neutron/atom interaction*/
    double h,l; /*thickness of the slab and length travelled*/
    double u; /*uniform random number*/
    double dd,d; /*direction of the neutron [0,pi]*/
    double x; /*position particle in the plate*/
    int n=10; /*number of samples*/
    int bounce; /*boolean value*/
    int i,r,b,t;
    r=0; b=0; t=0; /*reflected,absorbed and transmited neutrons*/
    /*generates randon values between 0 and 1*/
    /*dd = (float) rand()/RAND_MAX;*/
    for (i = 1; i <= n; i++)
    {
    x = 0.0;
    d = 0.0;
    dd = 0.0;
    c = 5.5545;
    cc = 0.0035;
    cs = 5.551;
    h = 10.00;
    bounce = 1;
    do {
    dd = (float) rand()/RAND_MAX;
    d=PI*dd;
    /*generates randon values between 0 and 1*/
    u = (float)rand()/RAND_MAX;
    l = -(1/c)*log(u);
    /*lenght travelled by the particle*/
    x = x + l*cos(d);
    //printf("value of x=%2.4f\n",x);
    if (x < 0.0) /*reflected*/
    {
    r = r + 1;
    bounce = 0;
    // printf("reflec r= %d\n",r);
    }
    else {
    if (x >= h) /*transmited*/
    {
    t = t+1;
    bounce = 0;
    // printf("trans t=%d\n",t);
    }
    else{
    if (u < cc/c)
    {
    b = b+1;
    bounce = 0;
    // printf("absorbed b=%d\n",b);
    }
    else d = u * PI;
    }
    }/*end first else*/
    } while (bounce = 1);
    } /*end for*/
    printf("Particles reflected = %d\n",dd);
    printf("Particles absorbed = %d\n",b);
    printf("Particles transmittedd = %d\n",b);
    }/*end main*/


    Please any help is more than welcome
     
Know someone interested in this topic? Share this thread via Reddit, Google+, Twitter, or Facebook

Have something to add?



Similar Discussions: MonteCarlo neutron transport
  1. Neutron beams (Replies: 4)

  2. Neutron Flux (Replies: 3)

Loading...