Experimental study for the decontamination of various surfaces from Mo using PVA/Borax/Al(OH) strippable hydrogel.

Polyvinyl alcohol (PVA) is a beneficial polymer capable of forming hydrogels helpful in a wide range of applications. Hydrogels based on cross-linking of PVA with borax, and able to incorporate with a decontaminating agent have been used in the decontamination of Mo from contaminated surfaces. Aluminum hydroxide has been introduced in the formulations of PVA-borax, to increase the gel efficiency for Mo decontamination from surfaces.

Polymeric gel for surface decontamination of long-lived gamma and beta-emitting radionuclides.

Synthesis and characterization of strippable polymeric-gel solution based on a water-soluble polymer (PVA), plasticizing agent (glycerol), and chelating agent (8-Hydroxyquinoline) for the surface decontamination from Cs and Co was carried out. Decontamination of glass and PVC surfaces was investigated in the present study, as a function of various chelating agents, gel-layer thickness, and radioactivity level. The decontamination efficiency was up to 95% for both radionuclides after 24 h of contact time with the contaminated surface.

Radiochemical signature of radium-isotopes and some radiological hazard parameters in TENORM waste associated with petroleum production: A review study.

Large amounts of TENORM waste (produced water, scale, and sludge) are created in oilfields around the world, presenting radiological risks to employees, the public, and the environment since activity concentrations of radioactive substances were above the exemption levels accredited by several authorities. Using the activity concentration of the radium-isotopes (Ra and Ra) in the waste, we determined the 'fingerprint' as a radiochemical signature and some relevant 'radiological hazard parameters' in this review. The majority of the reported residues take the form of radio-contaminated (produced water, scale, and sludge) generated in Egypt's oilfields or elsewhere include radium isotope activity concentrations (Ra) that exceed the international exemption limit.

Bentonite phosphate modified with nickel: Preparation, characterization, and application in the removal of Cs and Eu.

The present study concerns the sorption of Cs and Eu from low-level radioactive waste (LLW) by bentonite phosphate modified with nickel (BPN) sorbent material. BPN was synthesized using the precipitation method and characterized using various analytical techniques such as Fourier transform infrared (FT-IR), scanning electron microscope (SEM), X-ray fluorescence (XRF), and X-ray diffraction (XRD). The sorption data show that 90 min is enough time to reach equilibrium.

Examination of the parameters affecting of Rn emanation for some industrial and environmental samples using gamma-spectroscopy.

The present work aims to radiologically characterize five samples (monazite, zircon, scale waste originating from petroleum production, black sands and phosphate rocks) from different industrial applications and environments in the Egyptian territory. The first section of the present work discusses the measurement and analysis of Ra, Th and K concentrations. Moreover, the assessment of the hazard indices is given in terms of radium equivalent (Ra), external hazard index (H), internal hazard index (H), gamma-activity index (I) and alpha-activity index (I).

Purification of rad-waste arising from irradiated natural tin target towards tellurium-125m/antimony-125 radioisotope generator elaboration.

The present study introduces a new approach based on an irradiated tin target's impurity to produce aSb/Te radioisotope generator. A prepared generator gel matrix of zirconium-silico-tungstate was loaded with 6660 MBq (180 mCi) activity of the separated antimony. The loading and elution method has been studied as a function of the concentration of HSO acid solution.

Preparation, characterization and application of Mg/Fe Hydrotalcite as gamma sealed source for spectroscopic measurements.

A feasibility study was conducted to prepare, characterize and apply Mg/Fe Hydrotalcite composite as a core material of γ-sealed source used in spectroscopic measurements. Co-precipitation method was used to prepare the composite. To understand and define the physicochemical properties of the prepared composite, different analytical techniques were used.

Evaluation of synthetic aluminum silicate modified by magnesia for the removal of Cs, Co and Eu from low-level radioactive waste.

The present study concerns the preparation, characterization and testing of an inorganic ion exchanger Aluminum Silicate Modified Magnesia (ASMM). The ASMM composite was prepared using sol-gel technique and characterized by XRD, XRF, FTIR, TGA, DTA, SEM and surface area analysis. The capability of the prepared composite for the removal of (Cs, Co and Eu) from aqueous solution was evaluated.