Optimizing the shielding properties of strength-enhanced concrete containing marble
- 1. College of Industry and Energy Technology, New CairoTechnological University, Cairo (Egypt)
- 2. Department of Mathematics and Eng. Physics, Faculty of Engineering, Fayoum University, Fayoum (Egypt)
- 3. Department of Physics, Faculty of Science, Universityof Tabuk, Tabuk (Saudi Arabia)
- 4. Medical Radiation Research Center, USMERA, Uskudar University, Istanbul (Turkey)
- 5. Department of Radiotherapy, Vocational School of Health Services, Uskudar University, Istanbul (Turkey)
Description
The purpose of this study is to develop a low cost, locally produced concrete mixture with optimum marble content. The resulting mixture would have enhanced strength properties compared to the non-marble reference concrete, and improved radiation shielding proper-ties. To accomplish these goals five concrete mixtures were prepared, containing 0, 5, 10,15 and 20 % marble waste powder as a cement replacement on the basis of weight. These samples were subjected to a compressive strength test. The shielding parameters such as mass attenuation coefficients (μm), mean free path (MFP), effective atomic number (Zeff) and exposure build-up factors (EBF) were measured, and results were compared with those obtained using the WinXcom program and MCNPX code in the photon energy range of 0.015 - 3 MeV. Moreover, the macroscopic fast neutron removal cross-section (neutron attenuation coefficient) was calculated and the results presented. The results show that the sample containing 10 % marble has the highest compressive strength and potentially good gamma ray and neutron radiation shielding properties. (authors)
Availability note (English)
Also available at: https://doi.org/10.4279/PIP.120005Additional details
Identifiers
- DOI
- 10.4279/PIP.120005;
Publishing Information
- Journal Title
- Papers in Physics
- Journal Volume
- 12
- Journal Page Range
- 9 p.
- ISSN
- 1852-4249
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 52081160
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- CONCRETES; MARBLE; NEUTRONS; RADIATION DOSES; RADIATION PROTECTION; SHIELDING; SHIELDING MATERIALS
- Descriptors DEC
- BARYONS; BUILDING MATERIALS; DOSES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATERIALS; METAMORPHIC ROCKS; NUCLEONS; ROCKS
Optional Information
- Notes
- 35 refs., 2 tabs., 9 figs.