Monte-Carlo aided design of neutron shielding concretes

Bulletin of the Polish Academy of Sciences. Technical Sciences

A. Pola?skiDepartment of Interdisciplinary Applications of Physics, National Center for Nuclear Research, 05-400 Otwock-?wierk, PolandOther articles by this author:De Gruyter OnlineGoogle Scholar¹  T. PiotrowskiCorresponding authorFaculty of Civil Engineering, Warsaw University of Technology, 16 Armii Ludowej Ave., 00-637 Warsaw, PolandEmailOther articles by this author:De Gruyter OnlineGoogle Scholar²  J. SkubalskiFaculty of Physics and Applied Informatics, University of ?ód?, 149/153 Pomorska St., 90-236 ?ód?, PolandOther articles by this author:De Gruyter OnlineGoogle Scholar³  D.B. TefelskiLe Laboratoire d’Expertises Nucléaires en Assainissement et Conception, DSM/IRFU CEA – Saclay, Bât 130, F-91191 Gif sur Yvette Cedex, France2 Faculty of Physics, Warsaw University of Technology, 75 Koszykowa St., 00-662 Warsaw, PolandOther articles by this author:De Gruyter OnlineGoogle Scholar⁴  V. BlideanuLe Laboratoire d’Expertises Nucléaires en Assainissement et Conception, DSM/IRFU CEA – Saclay, Bât 130, F-91191 Gif sur Yvette Cedex, FranceOther articles by this author:De Gruyter OnlineGoogle Scholar⁴ 

[1]Department of Interdisciplinary Applications of Physics, National Center for Nuclear Research, 05-400 Otwock-?wierk, Poland

[2]Faculty of Civil Engineering, Warsaw University of Technology, 16 Armii Ludowej Ave., 00-637 Warsaw, Poland

[3]Faculty of Physics and Applied Informatics, University of ?ód?, 149/153 Pomorska St., 90-236 ?ód?, Poland

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

关键词: Keywords : nuclear;    neutron;    shielding;    concrete;    Monte Carlo Simulations;    MCNPX;    CINDER’90;   

DOI  :  10.2478/bpasts-2013-0015

学科分类：工程和技术（综合）

来源: Polska Akademia Nauk * Centrum Upowszechniania Nauki / Polish Academy of Sciences, Center for the Advancement of Science

【 摘 要 】

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

【 授权许可】

Unknown