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Microcrystalline SrB4O7:Eu3+ (SBO) synthesized using strontium carbonate, boric acid and europium chloride as precursors by solid state diffusion method with different concentrations of europium. The microcrystalline powder samples were annealed and quenched at different temperatures in the range of 400–900 °C for 2 h in air and were characterized by XRD, SEM, EDS techniques. The phosphor material with 0.2 mol% europium doping and annealed at 700 °C shows maximum TL intensity and PL studies show presence of Eu in 2 + and 3 + ionic states. The dosimetry characteristics show that the phosphor could be used for high dose measurements.

Microwave synthesized nano-sized Cu 2 ZnSnS 4 (CZTS) powder was irradiated with 6 MeV electrons, to investigate stability under radiation. The structural, optical, vibrational and morphological properties were explored using X-ray diffraction, UV–Visible spectroscopy, Raman spectroscopy and scanning electron microscope (SEM). The irradiated sample shows significant change in properties when compared with the pristine sample. X-ray peak broadening analysis has been used to estimate the crystallite size and lattice strain. Raman spectroscopy analysis confirms the transition of ordered kesteriteto disordered kesterite phase after electron irradiation at electron fluence of 4 × 10 15  e − /cm 2 . CZTS nanoparticles having hierarchical flower-like morphology starts agglomerating after electron irradiation as observed from SEM images. The sample did not amorphize up to the highest fluence4 × 10 15  e − /cm 2 employed in this study.

Al2O3:C is a well-known OSLD dosimetry phosphor but difficult to prepare due to its high melting point and carbon doping. In this paper carbon-doped Al2O3 nanophosphor (Al2O3:C-NP) was synthesized by a novel thermal plasma method using mixture of Al and C as starting materials in the presence of oxygen. Characterization of the material by XRD and TEM shows highly crystalline nanoparticles of γ-Al2O3 in the range of 10–100 nm. The maximum TL intensity with a very wide-range of doses was observed for the material containing 10 wt% of carbon when irradiated with γ rays and electron beam.

A radiochemical technique for estimation of 90Sr concentration by direct extraction of 90Y with bis (2-ethylhexyl) phosphate (HDEHP) in toluene was developed and standardized. About 90% 90Sr retained in the aqueous phase at the optimized pH 4–4.5. Cerenkov counting with 0.04 g mL−1 sodium salicylate as a wavelength shifter resulted in 7.5 fold increase its Cerenkov counting efficiency. The method was validated by estimating 90Sr in certified reference materials like, IAEA TEL 2016-03 drinking water, Spruce needle and IAEA-156 Clover. The interference of naturally occurring Ra and its β progeny especially Pb was eliminated by means of Cerenkov counting. Conventional radiochemical separation was used to compare 90Sr activity in effluent samples.

Zirconium silicide was synthesized on Si (100)/zirconium interface by means of swiftly moving 150 MeV Au ion beam. Thin films of zirconium (~60 nm) were deposited on Si (100) substrates in ultra high vacuum conditions using the electron-beam evaporation technique. The system was exposed to different ion fluencies ranging from 3 × 10 13 to 1 × 10 14  ions/cm 2 at room temperature. Synthesized zirconium silicide thin film reasonably affects the resistivity of the irradiated system and for highest fluence of 1 × 10 14  ions/cm 2 resistivity value reduces from 84.3 to 36 μΩ cm. A low resistivity silicide phase, C-49 ZrSi 2 was confirmed by X-ray analysis. Schottky barrier height was calculated from I–V measurements and the values drops down to 0.58 eV after irradiation at 1 × 10 14  ions/cm 2 . The surface and interface morphologies of zirconium silicide were examined by atomic force microscopy (AFM) and scanning electron microscopy (SEM). AFM shows a considerable change in the surface structure and SEM shows the ZrSi 2 agglomeration and formation of Si-rich silicide islands.

A radiochemical technique for estimation of uranium concentration and 234U/238U isotopic ratios by direct extraction of uranium with Bis (2-ethylhexyl) phosphate (HDEHP) in toluene at an optimized pH of 2–2.5 with an efficiency of 95–99 % was standardized. The extractant also acted as a scintillator for measurement of alpha radiations by liquid scintillation spectrometer (LSS). The method was validated by estimating the ratios of 234U/238U in certified reference materials like, IAEA RGU-1, Depleted uranium, Ammonium di-uranate samples and ore samples from different locations in India. Conventional radiochemical separation and alpha spectrometry of electroplated source was used to compare and ascertain the isotopic ratios of uranium.

The efficiency of ethylenediaminetetraacetic acid (EDTA) and diethylenetriaminepentaacetic acid (DTPA) in reducing the influence of salinity and extraction of iron and calcium into the organic phase along with uranium was studied. DTPA has been observed to be more suitable complexing agent compared to EDTA. Iron and calcium were found to be separated quantitatively with more than 95% recovery for uranium, facilitating its rapid and interference free analysis in the presence of DTPA. Uranium recovery under high salinity conditions was also observed to be in the range 89.7–98.6% in the presence of DTPA.

Orthophosphate-based phosphors have been used widely as efficient materials for the luminescence applications. Thermoluminescence (TL) properties of luminescent materials help us to find the suitability of the phosphors for the TL dosimetric application. In this work, a series of Dy 3+ doped and Mn 2+ -codoped sodium yttrium phosphate Na 3 Y(PO 4 ) 2 phosphors were synthesized via a solid-state reaction method and thermoluminescence behavior were studied. To observe the effect of the dopant and codopants on phase purity and crystalline structure of phosphors, X-ray diffraction method analyses were carried. In addition, the morphological images were examined; chemical composition and functional groups were confirmed. Herein, the Dy 3+ -doped and Mn 2+ -codoped Na 3 Y(PO 4 ) 2 phosphors were irradiated by 1 kGy-dose γ-radiation and Na 3 Y(PO 4 ) 2 :0.07Dy 3+ showed a intense TL intensity peak at 178 °C, whereas Mn 2+ -Na 3 Y(PO 4 ) 2 :0.07Dy 3+ , 0.07Mn 2+ phosphors showed at 134 °C. The effect of codopant Mn 2+ on the TL properties of Dy 3+ -doped Na 3 Y(PO 4 ) 2 phosphors and irradiation dose were investigated. The optimized Na 3 Y(PO 4 ) 2 :0.07Dy 3+ phosphor was showed a linear response to irradiation as a function of dose in the range of the 50 Gy–1.5 kGy. The glow curves were deconvolated and the TL kinetic parameters of phosphors were obtained by adopting various methods, revealing that the glow curves exhibited the second-order kinetics, and activation energies were calculated. The kinetic parameters of prepared samples were compared with the other TL materials. The obtained results confirm that the phosphors may have potential applications as TL dosimetry materials to measure low irradiation.

For cancer treatment, radiotherapy is one of the most trusted and efficient modalities in the healthcare field. Radiotherapy, for cancer treatment, commonly uses Gamma rays (Co-60 isotope) which is the most cost-effective and the most relevant method of treatment across the world. However, it becomes critically important to precisely measure the gamma dose incident on the patient’s body during treatment to improve the accuracy of dose delivery to the tumor. The present study was focused on the radiation measurement using as-developed thermoluminescence dosimeter (TLD) on cancer patients during radiotherapy. Herein, the Dy-doped BaAlF 5 phosphor was synthesized using the solid-state reaction method. For optimization, the BaAlF 5 :Dy phosphors were annealed at different temperatures varied from 500 to 950 °C to improve the thermoluminescence efficiency. The optimal glow curve was obtained for BaAlF 5 :Dy phosphor annealed at 900 °C, which peaked at 438 K. The phosphor showed linear dose–response from 50 cGy to 2 kGy and, beyond this level, it was saturated. The trapping parameters of the thermoluminescence glow curve, such as activation energy (E), and order of kinetics (b) were estimated by the glow curve deconvolution (GCD) method. Furthermore, the dose measurement study experiments were carried out on the cancer patient’s body to test the potentiality of phosphor for in vivo dosimetry. From the present study, it was inferred that the as-developed BaAlF 5 :Dy phosphors can measure doses as low as 50 cGy. The newly explored promising dosimetric properties of BaAlF 5 :Dy phosphors make them potential TLD materials and provide new prospects for utilizing these phosphors in the field of radiation therapy, medical dosimetry, and healthcare applications.

The flux weighted average cross sections of the 141 Pr(γ,n) 140 Pr, 160 Gd(γ,n) 159 Gd and 162 Er(γ,n) 161 Er nuclear reactions induced by 10 and 15 MeV energy bremsstrahlung photons are measured with offline gamma spectrometry. The cross sections are reported with detailed uncertainties in the associated parameters. The measured cross sections are compared with the theoretical cross sections calculated using TALYS 1.95 code for eight different gamma strength functions. The average cross sections are also compared with the Geant4 Monte Carlo simulations of the nuclear reactions induced by bremsstrahlung photons. The measured cross sections are important for the nuclear database and nuclear astrophysics research.