Download A Monte Carlo Primer: Volume 2 by Stephen A. Dupree, Stanley K. Fraley PDF

By Stephen A. Dupree, Stanley K. Fraley

In quantity 1, A Monte Carlo Primer - a pragmatic method of Radiation delivery (the "Primer"), we strive to supply an easy, handy, and step by step method of the advance, easy figuring out, and use of Monte Carlo equipment in radiation delivery. utilizing the computer, the Primer starts off by way of constructing uncomplicated Monte Carlo codes to unravel uncomplicated shipping difficulties, then introduces a educating software, the Probabilistic Framework Code (PFC), as a regular platform for assembling, checking out, and executing many of the Monte Carlo concepts which are awarded. This moment quantity makes an attempt to proceed this method by utilizing either customized Monte Carlo codes and PFC to use the strategies defined within the Primer to acquire options to the routines given on the finish of every bankruptcy within the Primer. a comparatively modest variety of workouts is integrated within the Primer. a few ambiguity is left within the assertion of the various routines as the reason isn't to have the person write a selected, uniquely right piece of coding that produces a particular quantity consequently, yet relatively to motivate the person to contemplate the issues and advance extra the strategies defined within the textual content. simply because as a rule there's multiple option to resolve a Monte Carlo shipping challenge, we think that operating with the options illustrated via the workouts is extra vital than acquiring a person specific solution.

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Sumsq = O. signet = 1. CAT (nrrax) ) WRITE(*, *) sum, sig SIDP END Discussion 3. Monte Carlo Modeling of Neutron Transport 29 An alternative approach to this problem involves deriving the pdf for the exponential distribution from first principles. The probability dP that a neutron will travel a distance x without suffering a collision in a uniform, homogeneous material with a macroscopic total cross section L(, and then will experience a collision in dx about x is The probability dP is the product ofLh which is the probability per unit path length of a neutron experiencing a collision in the material in question; times the path length dx; times eoE(x, which is the probability that the neutron will reach the point x without suffering a collision.

5. 5. 3 in which there was no bubble. The results for the number of reflected particles varies between 48700 and 51336 per 10 5 start particles as the position of the beam varies between x = 0 and x = 1. 5 mfp deep in the slab we see the effect of its location relative to the position of the incident beam on the number of particles that are reflected from the slab. The estimated uncertainty in the number of reflected particles, 3. 5. 5. 4 Statement of the problem 4. 3 were obtained assuming a binomial distribution in the estimates.

Txt ') a=O •dO; b=tpi ! a,b are l<:lW:r and uwer limits of integral ! OdO ! 6) CO 100 J=l,nsamples ! fltm () generates a randan nurrtler in (0, 1) r=fltmO , pick unbiased x x--a+ (b-a) *r score=f(x); sumf=sumf+soore; sumfsq=sumfsq+score*~2 ! score unbiased functioo , pick biased x x=tpi*(l-DSQRT(r)) score=g(x); sumg=sumg+score; sumgsq=sumgsq+score*~2 ! score biased function 100 CCNrINUE J=nsarrples stdev = DSQRT(DABS(sumfsq/j - (sumf/j)**2)) WRITE(6,14)j,sumf/j,stdev,stdev/SQRT(~T(j)) ! unbiased results WRITE(6,14)j,sumg/j,stdev,stdev/SQRT(~T(j)) !

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