Assessment of a polymeric composite as a radiation attenuator and a restoration mortar for cracking in biological shields
| Autor: | I.E. Hasan, A.T. Gheith, R.A. Rizk, N.L. Helal, M.A. El-Sarraf, Amal A. El-Sawy, A. El-Sayed Abdo |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2020 |
| Předmět: |
Attenuator (electronics)
Nuclear and High Energy Physics Materials science 010308 nuclear & particles physics Astrophysics::High Energy Astrophysical Phenomena attenuation parameters Composite number biological shield Shields Radiation lcsh:Atomic physics. Constitution and properties of matter 01 natural sciences 030218 nuclear medicine & medical imaging lcsh:QC170-197 03 medical and health sciences Cracking 0302 clinical medicine neutron and gamma-ray spectra 0103 physical sciences mcnp code composite Composite material Mortar |
| Zdroj: | Âderna Fìzika ta Energetika, Vol 21, Iss 4, Pp 361-368 (2020) |
| ISSN: | 2074-0565 |
| Popis: | This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composite for radiation attenuation at multiple applications related to nuclear installations, as well as restoration mortar for cracking developed in concrete biological shields. The mechanical properties (flexural, compressive, and impact strengths) and the physical properties (water absorption, porosity, and dry bulk density), each, have been performed to label the composite integrity for practical application. In practice, attenuation properties have been performed by using a collimated beam emitted from spontaneous fission 252Cf (100 μg) neutron source and neutron gamma spectrometer with stilbene scintillator. The pulse shape discrimination technique which would come of the zero cross over method was used to measure the fast neutron and gamma-ray spectra. Thermal neutron fluxes have been measured by using the thermal neutron detection system and the BF-3 detector. The attenuation parameters: precisely, macroscopic effective removal cross-sections ΣR (cm-1), macroscopic cross-sections Σ (cm-1), and total attenuation coefficients μ (cm-1) of fast and thermal neutrons and total gamma-rays respectively were evaluated using the attenuation relations. Also, the MCNP5 code and MERCSF-N program have been used to compute the parameters theoretically. When applicable, measured and calculated results were compared, and it tells us a comprehensive agreement. |
| Databáze: | OpenAIRE |
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