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PENELOPE 2003 - OECD Nuclear Energy Agency

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Chapter 1<br />

Monte Carlo simulation. Basic<br />

concepts<br />

The name “Monte Carlo” was coined in the 1940s by scientists working on the nuclear<br />

weapon project in Los Alamos to designate a class of numerical methods based on the<br />

use of random numbers. Nowadays, Monte Carlo methods are widely used to solve<br />

complex physical and mathematical problems (James, 1980; Rubinstein, 1981; Kalos<br />

and Whitlock, 1986), particularly those involving multiple independent variables where<br />

more conventional numerical methods would demand formidable amounts of memory<br />

and computer time. The book by Kalos and Whitlock (1986) gives a readable survey of<br />

Monte Carlo techniques, including simple applications in radiation transport, statistical<br />

physics, and many-body quantum theory.<br />

In Monte Carlo simulation of radiation transport, the history (track) of a particle is<br />

viewed as a random sequence of free flights that end with an interaction event where<br />

the particle changes its direction of movement, loses energy and, occasionally, produces<br />

secondary particles. The Monte Carlo simulation of a given experimental arrangement<br />

(e.g. an electron beam, coming from an accelerator and impinging on a water phantom)<br />

consists of the numerical generation of random histories. To simulate these histories we<br />

need an “interaction model”, i.e. a set of differential cross sections (DCS) for the relevant<br />

interaction mechanisms. The DCSs determine the probability distribution functions<br />

(PDF) of the random variables that characterize a track; 1) free path between successive<br />

interaction events, 2) kind of interaction taking place and 3) energy loss and angular<br />

deflection in a particular event (and initial state of emitted secondary particles, if any).<br />

Once these PDFs are known, random histories can be generated by using appropriate<br />

sampling methods. If the number of generated histories is large enough, quantitative<br />

information on the transport process may be obtained by simply averaging over the<br />

simulated histories.<br />

The Monte Carlo method yields the same information as the solution of the Boltzmann<br />

transport equation, with the same interaction model, but is easier to implement<br />

(Berger, 1963). In particular, the simulation of radiation transport in finite samples is

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