- Tytuł:
- Monte-Carlo aided design of neutron shielding concretes
- Autorzy:
-
Tefelski, D.
Piotrowski, T.
Polański, A.
Skubalski, J.
Blideanu, V. - Powiązania:
- https://bibliotekanauki.pl/articles/201978.pdf
- Data publikacji:
- 2013
- Wydawca:
- Polska Akademia Nauk. Czytelnia Czasopism PAN
- Tematy:
-
nuclear
neutron
shielding
concrete
Monte Carlo simulation
MCNPX
CINDER’90 - Opis:
- The process of design of building composites, like concrete is a complex one and involves many aspects like physical and mechanical properties, durability, shielding efficiency, costs of production and dismantlement etc. There are plenty of parameters to optimize and computer tools can help to choose the best solution. A computer aided design plays an important role nowadays. It becomes more accurate, faster and cheaper, so laboratories often apply computer simulation methods prior to field testing. In case of nuclear engineering, the radiation shielding problems are of much importance, because safety of such facilities is a key point. In this article the most effective methods for neutron shielding studies based on Monte-Carlo simulations of neutron transport and nuclide activation studies in concrete are presented. Two codes: MCNPX and CINDER’90 are extensively used to compare the shielding efficiency of commonly used concretes and to study the influence of concentration of B, Ba and Fe elements on shielding efficiency.
- Źródło:
-
Bulletin of the Polish Academy of Sciences. Technical Sciences; 2013, 61, 1; 161-171
0239-7528 - Pojawia się w:
- Bulletin of the Polish Academy of Sciences. Technical Sciences
- Dostawca treści:
- Biblioteka Nauki