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Production of New Nanocomposites for Neutron and Gamma Shielding and Modeling of the Attenuation Phenomena Using Computational Methods

Safavi, Mohammad Reza | 2022

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 55919 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Outokesh, Mohammad; Vosoughi, Naser; Kiani, Mohammad Amin
  7. Abstract:
  8. If nuclear radiation is not weakened and absorbed, it can cause serious damage to human devices or the environment. Dual-purpose dry casks are one of the sources of nuclear radiation production as a place to keep the spent fuel assemblies. One of the ways to protect against them is to use shield. One of the most common of them is composite shield. The composite used in this study has a polymer matrix. The matrix of the used polymer is epoxy resin. In this study, two separate composites have been made to attenuate neutron and gamma radiation. In this thesis, first, by using the MCNPX code, the necessary simulations for the design and construction of composite shields have been carried out. Then, using epoxy resin and adding gadolinium oxide and bismuth oxide, epoxy/gadolinium oxide and epoxy/bismuth oxide composites were designed and manufactured, respectively, and were irradiated for protection against neutron and gamma sources. Among the tests and analyzes used for the samples in this study are: Inductively Coupled Plasma (ICP), Static Light scattering (SLS), X-ray Diffraction (XRD), Scanning Electron Microscope (SEM), Mechanical Strength (Tensile), thermogravimetric analyze (TGA) and Fourier Transform Infrared Spectrometer (FTIR). It was found that the composite sample containing 5% of gadolinium oxide and about 2.5 cm thick as the optimal neutron shielding sample can absorb all the emitted neutrons. Also, the composite sample containing 30% of bismuth oxide with a thickness of 4.5 cm is designed as an optimal sample, capable of absorbing 30% of gammas from the cobalt source, 50% of the gammas from the cesium source and 100% of the gammas from the americium source
  9. Keywords:
  10. Gamma Rays ; Composite Shields ; Nuclear Reactions ; Monte Carlo N-Particle (MCNP)Code ; Neutron Radiation ; Dry Storage Cask ; Dual Purpose Dry Cask ; Epoxy Coating

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