Monte-Carlo aided design of neutron shielding concretes

• Autorzy: Tefelski D. , Piotrowski T. , Polański A. , Skubalski J. , Blideanu V.
• Języki publikacji: EN

Abstrakty

EN

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.

Słowa kluczowe

EN

nuclear; neutron; shielding; concrete; Monte Carlo simulation; MCNPX; CINDER’90

• Wydawca: Polska Akademia Nauk, Wydział IV Nauk Technicznych
• Czasopismo: Bulletin of the Polish Academy of Sciences. Technical Sciences
• Rocznik: 2013
• Tom: Vol. 61, nr 1
• Strony: 161--171
• Opis fizyczny: Bibliogr. 26 poz., rys., tab.

Twórcy

autor

Tefelski D.

autor

Piotrowski T.

autor

Polański A.

autor

Skubalski J.

autor

Blideanu V.

• Le Laboratoire d’Expertises Nucléaires en Assainissement et Conception, DSM/IRFU CEA – Saclay, Bât 130, F-91191 Gif sur Yvette Cedex, France

Bibliografia

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