Naslov
Monte Carlo Codes for Neutron Buildup Factors

Autori
Trontl, Krešimir ; Pevec, Dubravko ; Matijević, Mario

Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni

Izvornik
9th International Conference on Nuclear Option in Countries With Small and Medium Electricity Grids / Grgić, Davor ; Šimić, Zdenko ; Vuković, Igor - Zagreb : Croatian Nuclear Society, Unska 3, 10000 Zagreb, 2012, 89-89

ISBN
978-953-55224-5-4

Skup
9th International Conference on Nuclear Option in Countries With Small and Medium Electricity Grids

Mjesto i datum
Zadar, Hrvatska, 03.06.2012. - 06.06.2012

Vrsta sudjelovanja
Poster

Vrsta recenzije
Međunarodna recenzija

Ključne riječi
Monte Carlo; neutron build-up factors; point-kernel method; SCALE4.4; SCALE6.0; MCNP5

Sažetak
The point-kernel method is a widely used practical tool for gamma ray shielding calculations. However, application of that method for neutron transport simulations is very limited. The accuracy of the method strongly depends on the accuracy of buildup factors used in the calculations, where, for example dose buildup factor can be represented as the ratio of dose at the detector point and uncollided dose at the same point. Buildup factors are usually obtained by using appropriate computer codes, either based on discrete ordinates transport method or Monte Carlo approach. Since these codes put strong demands on computer resources, they are applied on a limited number of shielding configurations and an attempt is made to use obtained results and formulate an empirical expression for buildup factors estimation. Due to high physical complexity of neutron transport through shielding material it is very hard to perform parameterisation in order to establish adequate empirical formula. Existing formulas are very limited and are usually applicable to a very limited neutron energy range for few commonly used shielding materials, mostly in monolayer configuration. Recently, a new approach has been proposed for determination of gamma ray buildup factors for monolayer, as well as multi layer shielding configurations covering a wide gamma ray energy range. The new regression model is based on support vector machines learning technique, which is an extension of support learning theory. Development of named regression model required a large number of experimental data obtained by Monte Carlo computer code. More than 7000 Monte Carlo runs were required. Since neutron transport is likely to require even more experimental data in order to generate a model of reasonable accuracy, the choice of appropriate Monte Carlo code is a very important task. One has to take into account the accuracy as well as the time required for input preparation and running the code. What also has to be considered is the possibility of the code to be incorporated in an algorithm for automated generation of experimental data. In this paper three Monte Carlo codes are considered, namely SCALE4.4 code package (SAS3 sequence), SCALE6.0 code package (MAVRIC sequence), and MCNP5. A simple experimental setup based on a point isotropic source in spherical single and double layer shield is modelled, and the codes are examined on previously mentioned issues.

Izvorni jezik
Engleski

Znanstvena područja
Elektrotehnika

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