Published April 2009 | Version v1
Book

Monte Carlo applications to radiation shielding problems

  • 1. Safety Research Institute, Atomic Energy Regulatory Board, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

Monte Carlo methods are a class of computational algorithms that rely on repeated random sampling of physical and mathematical systems to compute their results. However, basic concepts of MC are both simple and straightforward and can be learned by using a personal computer. Uses of Monte Carlo methods require large amounts of random numbers, and it was their use that spurred the development of pseudorandom number generators, which were far quicker to use than the tables of random numbers which had been previously used for statistical sampling. In Monte Carlo simulation of radiation transport, the history (track) of a particle is viewed as a random sequence of free flights that end with an interaction event where the particle changes its direction of movement, loses energy and, occasionally, produces secondary particles. The Monte Carlo simulation of a given experimental arrangement (e.g., an electron beam, coming from an accelerator and impinging on a water phantom) consists of the numerical generation of random histories. To simulate these histories we need an interaction model, i.e., a set of differential cross sections (DCS) for the relevant interaction mechanisms. The DCSs determine the probability distribution functions (pdf) of the random variables that characterize a track; 1) free path between successive interaction events, 2) type of interaction taking place and 3) energy loss and angular deflection in a particular event (and initial state of emitted secondary particles, if any). Once these pdfs are known, random histories can be generated by using appropriate sampling methods. If the number of generated histories is large enough, quantitative information on the transport process may be obtained by simply averaging over the simulated histories. The Monte Carlo method yields the same information as the solution of the Boltzmann transport equation, with the same interaction model, but is easier to implement. In particular, the simulation of radiation transport in complex geometries is straightforward, while even the simplest finite geometries (e.g., thin foils) are very difficult to be dealt with by the transport equation. The main drawback of the Monte Carlo method lies in its random nature: all the results are affected by statistical uncertainties, which can be reduced at the expense of increasing the sampled population, and, hence, the computation time. Under special circumstances, the statistical uncertainties may be lowered by using variance-reduction techniques. Monte Carlo methods tend to be used when it is infeasible or impossible to compute an exact result with a deterministic algorithm. The term Monte Carlo was coined in the 1940s by physicists working on nuclear weapon projects in the Los Alamos National Laboratory

Part of:
Applications of Monte Carlo methods in nuclear science and engineering

Additional details

Publishing Information

Publisher
Department of Atomic Energy
Imprint Place
Mumbai (India)
ISBN
978-81-8372-047-2
Imprint Title
Applications of Monte Carlo methods in nuclear science and engineering
Imprint Pagination
448 p.
Journal Page Range
p. 192-214

Conference

Title
applications of Monte Carlo methods in nuclear science and engineering
Acronym
DAE-BRNS theme meeting
Dates
21-24 Apr 2009
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
41020898
Subject category
S72: PHYSICS OF ELEMENTARY PARTICLES AND FIELDS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIFFERENTIAL CROSS SECTIONS; M CODES; MONTE CARLO METHOD; RADIATION TRANSPORT; RANDOMNESS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; CROSS SECTIONS

Optional Information

Notes
3 refs., 5 figs., 1 ill.