Volume 113, Issue 5

A very brief overview of the hitherto investigated production routes of 86g Y is given, and a comparative analysis of its production via the two low-energy reactions, namely (p,n) and (d,2n) on 96.4 % enriched 86 Sr as target material, is presented. Based on our recent cross-section measurements, the calculated yields of 86g Y via the two reactions were compared, and the levels of co-produced isotopic impurities were estimated. At low-energy medical cyclotrons ( E p  < 20 MeV; E d  < 10 MeV) the use of the (p,n) reaction is superior, both in terms of the yield of 86g Y and the levels of radionuclidic impurities. At medium-sized cyclotrons, on the other hand, the (d,2n) reaction leads to higher yield of 86g Y, but the level of radionuclidic impurities is also higher. The method of choice for production of 86g Y thus remains the (p,n) reaction on enriched 86 Sr.

A new systematics was developed that predicted the (n,f) nuclear reaction cross sections for thorium isotopes in the mass number range 228 ≤  A  ≤ 234. The TALYS-1.95 and EMPIRE-3.2.3 nuclear computer codes were used to do calculations that validated the results. Semi-empirical formulas are used for a variety of thorium isotopes that divide to the third fission level. The excitation functions of the 228 Th (n,f), 229 Th (n,f), 230 Th (n,f), 231 Th (n,f), 232 Th (n,f), 233 Th (n,f), and 234 Th (n,f) nuclear reactions have been calculated at incident neutron energy ranging between 1 and 20 MeV. In addition to evaluated nuclear data files, such as JENDL 3.3, TENDL-2021, ENDF (B-VII.1), JENDL-4, BROND-3.1, EAF-2010, and ROSFOND-2010, experimental data from the EXFOR library were compared with our calculation. Overall, there is good agreement between the new semi-empirical formula, computer codes, evaluated files and experimental data fission cross sections.

The extraction of neptunium in the +IV, +V, and +VI oxidation states was studied in irradiated solutions of 30 % tri- n -butyl phosphate (TBP) in dodecane as well as in synthetic mixtures of TBP with its primary radiolysis product, di- n -butyl phosphoric acid (HDBP). Extraction of all three oxidation states was increased by irradiation, with the most dramatic effect for Np(IV). Without stabilization of the neptunium oxidation state, the irradiated organic phase displayed redox activity toward the Np(VI/V) couple, achieving a Np(VI):Np(V) ratio set by absorbed dose, independent of starting oxidation state. In synthetic TBP-HDBP mixtures, Np(VI) was extracted better than in the irradiated case, while Np(IV) displayed similar behavior between the two systems. The presence of HDBP resulted in greater equilibrium Np(VI):Np(V) ratios when contacting a Np(V) solution in 4 M HNO 3 with the synthetic mixture. Tetravalent neptunium also formed precipitates in the presence of HDBP at low acidities or high HDBP concentrations. All evidence points toward an ion-exchange extraction mechanism, where DBP − , rather than nitrate, coordinates to Np(IV) or Np(VI). Reductive stripping of Np(VI) from degraded organic phases using nitrous acid was unsuccessful, indicating that Np(VI) reduction is inhibited by the presence of HDBP.

Present study is the first attempt on the application of ionic liquid (IL) for the extraction of 211 At with the 7.21-h-half-life in targeted alpha-particle therapy. We produced the nuclide to investigate utilities of several ionic liquids, namely, [C 4 mim][Tf 2 N], [C 6 mim][Tf 2 N], [C 8 mim][Tf 2 N], [C 8 mim][PF 6 ], and [C 8 mim][BF 4 ] in solvent extraction and back extraction for the practical application of a 211 Rn/ 211 At generator. Astatine extraction with ionic liquids was investigated in detail in this study, and the extraction mechanism was elucidated for the first time.

The main purpose of this paper is to aid in solving the ink waste problem resulting from different printing processes. So, superabsorbent copolymer hydrogel composed of Poly(N-Vinyl-2- pyrrolidone) and Poly (Acrylic acid) P(NVP/AAc) was prepared using gamma radiation techniques. The study investigated the effect of irradiation dose on gelation percentage which revealed that maximum gelation percentage obtained at irradiation dose 20 kGy. Hydrogels prepared at 10 kGy exhibited a good gelation percentage 99 % corresponding to a maximum swelling percentage (∼12,000 %) at pH 11 and increased with increasing temperature to reach 48,000 % at 60 °C. Swelling kinetic studies revealed a faster water diffusion and higher swelling percentages in hydrogels prepared at 10 kGy Treatment of ink solution demonstrated the tremendous ability of P(NVP/AAc) superabsorbent hydrogels to recover water based on forward osmosis and reducing waste volume of ink and separation of water from the solid content of ink waste by 87.5 %. Additionally, the water retention of the hydrogels was studied and it was observed that water evaporation was approximately 75 % of water content within 50 h over indicating the high ability of superabsorbent hydrogels in both absorption and retains water molecules. DFT analysis revealed highest a cumulative pore volume equal 84 cc/g for P(NVP/AAc) prepared at the lowest irradiated dose corresponding to highest surface areas 136 m 2 /g. Differential Scanning Calorimeter analysis (DSC) analysis indicated changes in crystallinity and increasing in thermal stability with increasing irradiation dose. Scanning Electron Microscope (SEM) Fourier Transfer Infrared Spectroscopy (FTIR) were investigated and confirmed the functional groups and porous hydrogel structure and indicated that the a potential lack of attraction to ink molecules and a preference for water absorption.

The complexity of mineral processing investigations is rapidly increasing the demand for precise composition and phase distribution analysis in complicated ore assemblages. Here, we present a systematic mineralogical approach to assess the chemical composition of geological ores (namely: S-7, S-8, S-12, S-13, S-15, S-17 and S-18) by key characterization techniques including: X-ray diffraction (XRD), Scanning electron microscopy with energy dispersive X-ray analysis (SEM-EDX) and Fourier transform infrared spectroscopy (FTIR). The XRD analyses reveal that the ores are comprised of different minerals including: quartz, microcline, albite, kaolinite, muscovite, barite, fluorite, calcite and hydroxyapatite. The microstructural, morphological and surface topography are determined by SEM using secondary electron (SE) imaging while backscattered electron (BSE) imaging effectively differentiates the various regions within the ore samples according to their compositional difference. Both qualitative and quantitative elemental analyses are provided by EDX spectra. A total of 25 elements were detected, including rare-earth elements as well. Moreover, the functional groups which are the finger prints of the minerals present in the ores were investigated by FTIR spectroscopy. The IR absorption bands are well assigned and interpreted. The experimental results from XRD, SEM-EDX and FTIR are well associated with one another and successfully classify the ore samples on the basis of their lithologies.

This study examined the elastic, and radiation resistance of CdO–B 2 O 3 –P 2 O 5 – Na 2 O glasses. The density observed increased from 3.42 to 4.87 g/cm 3 in conjunction with the increase in CdO content. As the CdO increases, the ( V L ) increases from 4,690 to 5,040 m/s. Similarly, the ( V S ) increases from 2,045 to 2,275 m/s. Furthermore, the elastic moduli showed a linear increase with the increment of CdO concentration. The evaluation of multiple basic radiation attenuation variables was used to determine the radiation shielding of these glasses. This indicates that the addition of CdO has a positive influence on the glass’s ability to attenuate γ radiation. This suggests that this specific glass composition is effective in attenuating γ , making it appropriate for radiation shielding purposes.

Recently, cigarettes, vapes, and hookahs are very common in Kurdistan region, Iraq. As a result, natural radionuclides, such as 222 Rn, 226 Ra, 214 Po, and 218 Po, are inhaled by smoking which increases the possibility of cancer. In this study, blood samples were taken from volunteers at seven age groups. A solid state nuclear track detector (CR-39) was used to detect radon gas and their daughters in male blood samples. The results show that the mean values of alpha emitters concentrations from 222 Rn, 226 Ra, 214 Po, and 218 Po in powdered blood samples for cigarette, vape, hookah smokers and non-smokers were 207.78, 239.02, 251.87, 25.92 Bq m −3 , 0.794, 0.913, 0.962, 0.099 Bq kg −1 , 29.686, 34.150, 35.985, 3.703 Bq m −3 on the walls of the chamber (POW), and 36.202, 41.645, 43.884, 4.516 Bq m −3 on the face of detector (POS) respectively. The findings demonstrate that age and smoking affect all alpha emitters. It was noted that hookah smokers had a higher alpha emitters concentration than other groups. The mean value for smokers were within the recommended global exposure limit of 200 Bq m −3 for 222 Rn, while non-smokers were well below it. Then, absorbed effective dose by an inhalation of 222 Rn and for smokers’ lung have been found for cigarette, vape, hookah smokers and non-smokers which were within the recommended limit (3–10 mSv y −1 ) for smokers as recommended by ICRP. In addition, the mean case of lung cancer for smokers were within the EU limit. Results indicate that smoking causes an increase in the alpha emitters concentration in the blood.