Monte-Carlo aided design of neutron shielding concretes
Dariusz Tefelski , Tomasz Piotrowski , V. Blideanu , A. Polanski , J. Skubalski
AbstractThe 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.
|Journal series||Bulletin of the Polish Academy of Sciences, Technical Sciences, ISSN 0239-7528|
|Publication size in sheets||0.5|
|Keywords in English||CINDER'90; Design of buildings; MCNPX; Monte-Carlo simulations; Neutron transport; Nuclear; Physical and mechanical properties; Shielding efficiency, Computer aided design; Computer simulation; Intelligent systems; Monte Carlo methods; Neutrons; Radiation shielding; Shielding, Concretes|
|ASJC Classification||; ; ; ;|
|Score|| = 25.0, 12-07-2020, ArticleFromJournal|
= 25.0, 12-07-2020, ArticleFromJournal
|Publication indicators||= 4; = 3; = 15.0; : 2013 = 1.411; : 2013 = 1.0 (2) - 2013=1.107 (5)|
|Citation count*||16 (2020-09-14)|
* presented citation count is obtained through Internet information analysis and it is close to the number calculated by the Publish or Perish system.