Oral presentation (Best Presenter)

This work examines the structural, electronic, mechanical, optical, and thermal properties of Cr2AC (A = Si, Al, Ga, Ge, and P) MAX phases using density functional theory. These properties are investigated through first-principles calculations within the generalized gradient approximation using the CASTEP software package. The Cr2AC phases exhibit metallic behavior, as confirmed by their electronic band structures, with no bandgap present. Regarding mechanical properties, Cr2SiC and Cr2GeC display superior ductility due to their covalent bonding, while Cr2AlC and Cr2GaC are more brittle due to ionic bonding. The elastic constants confirm the mechanical stability of these compounds, and the analysis of their anisotropic mechanical behavior indicates varying degrees of direction-dependent elasticity. For optical properties, reflectivity and refractive indices calculations suggest that these materials could be useful for optoelectronic applications. Thermal properties, including Grüneisen parameters (γ) and Debye temperatures (ΘD), indicate that Cr2AlC and Cr2PC exhibit exceptional thermal stability, making them promising candidates for thermal barrier coatings. These MAX phases are mechanically stable, and their tunable properties, driven by A-site substitution, expand the range of potential applications in areas such as high-temperature and optoelectronic devices used in hostile environments.

167Tm is an effective radioisotope for use in theragnostic purposes. This study aims to find the best alternative routes for producing 167Tm for appropriate cancer therapy and diagnostics. In this study, we comprehensively analyzed production cross-sections of 167Tm and investigated the behavior of these reactions using six different level density models and refined optical model potential (OMP) parameters with the nuclear reaction code TALYS 1.96. Using this code, we estimated the specific activity and production yield for promising production routes. For characterizing the 167Tm isotopes, the energy distribution of 167Tm was also analyzed for each prominent reaction by particle and heavy ion transport code system (PHITS). The maximum specific activity was estimated as 52.6–75.2 GBq/g with a production yield of 20.2–32.7 GBq/mAh for the route 169Tm(p,x)167Tm. The experimental value was reproduced with good agreement by TALYS adjusting different OMP parameters. 169Tm(p,x)167Tm is the alternative route for producing 167Tm, for which TALYS can reproduce the result more accurately.

The utilization of actinium-225 (225Ac) radionuclides in targeted alpha therapy for cancer was initially outlined in 1993. Over the past two decades, substantial research has been conducted, encompassing the establishment of 225Ac production methods, various preclinical investigations, and several clinical studies. Currently, there is a growing number of compounds labeled with 225Ac that are being developed and tested in clinical trials. In response to the increasing demand for this nuclide, production facilities are either being built or have already been established. This article offers a concise summary of the present state of clinical advancements in compounds labeled with 225Ac. It outlines various processes involved in the production and purification of 225Ac to cater to the growing demand for this radionuclide. The article examines the merits and drawbacks of different procedures, delves into preclinical trials, and discusses ongoing clinical trials.

In a fusion reactor, DT reactions produce huge amount of neutrons which hit the structure material and produce heat and damages. To understand the production of nuclear heating and material damages, study of double differential cross section (DDX), energy differential cross section (EDX), penetrating range of incident particles and stopping power of target element was calculated for 52Cr (n, p) and 52Cr (n, a) reactions. The calculated data have been compared with the suitable experimental data collected from EXFOR and other. The contribution of compound, pre-equilibrium and direct reaction processes has been analyzed for the entire cross section calculation. The emission of charged particles at different angles has been discussed based on the reaction processes. Parameter adjustment has been applied to fit the experimental data.

Vol. 42(3)

Abstract: Neutron induced 55Mn reactions were evaluated in the energy range 0.001 MeV to 40 MeV using TALYS1.95 computer code. During this evaluation, local and global parameterisations of Koning and Delaroche were used in nuclear optical model. Comparisons were made with experimental data, collected from EXFOR and other sources. Some optical model parameters (OMP) were needed to be adjusted for better agreement between theoretical calculations and experimental findings. Various evaluated libraries such asENDF, JENDL etc. were checked and compared with our evaluation. TALYSevaluation showedbetter agreement when parameters were adjusted.

This study evaluated the production routes of the medically essential radioisotope 72As from the stable isotopes of gallium, germanium, arsenic, and selenium, where four alpha-induced reactions: 69Ga(α, n)72As, 71Ga(α, 3n)72As, 70Ge(α, np)72As, and 72Ge(α, nt)72As and five proton-induced reactions: 72Ge(p, n)72As, 73Ge(p, 2n)72As, 74Ge(p, 3n)72As, 75As(p, nt)72As, and 74Se(p, 2np)72As are evaluated using three phenomenological and one microscopic nuclear level density models in different energy ranges. The investigation compares the calculated results based on the chosen models and the experimental data collected from the EXFOR data library. Statistical factors H, D, and R were also computed to determine the level density model with the best fit to the experimental data. Some level density parameters were adjusted to enrich the fits further, and integral yield vs energy was calculated using the best-fitted models.

Invited Talk

Wiley-VCH, GmbH

DOI: 10.29328/journal.ijpra.1001063

Oral presentation

Poster presentation

Collection of Poems

177Lu is used in medical research for various radiotheragnostic applications in nuclear medicine because of its various isotope properties. In this paper, we calculated the cross sections and production yields of the Lu isotope from different reactions X+176,174Lu and X+176Lu in energy levels from 0.001 to 100 MeV by using TALYS-1.96 and EMPIRE-3.2.2. Although n, d, and t reactions show an outstanding crosssection performance, α and t reactions show very impactful integral yield data. For the potential outcomes, these estimates are analyzed by comparing them to TENDL-2019 and EMPIRE-3.2.2.

Elsevier

Oral Presentation

Oral Presentation

Elsevier

American Physiological Society

American Chemical Society

Elsevier

Vol. 33(1)

East Eur. J. Phys. 3. 55-61

Vol. 94

According to IAEA TRS-398 protocol the Tissue Phantom Ratio, TPR20, 10, is used as a quality index for the megavoltage photon beam in external beam radiotherapy. This work presents a calculation of TPR20, 10, in two high energy photon modes using FC65-G thimble type cylindrical ionization chambers with the help of Monte Carlo method. The MCNP (version MCNP5) code was used for the simulation of photon beams delivered by Varian-2300CD Clinac accelerator head. The TPR20, 10 values were also measured experimentally using the same chamber. The calculation of TPR20, 10 using MC simulation showed good agreement with our experimentally determined values. The TPR20, 10 discrepancies of Monte Carlo and experimental values were found within 3.12% and 2.7% for 6 MV and 10 MV photon beams respectively. As MCNP simulated values showed good agreement with experimentally determined values, so this simulation technique should be applicable for the further research in reference dosimetry.

Invited talk

Physics Open, 5 (100052) 2020

As 27Al has important applications in reactor science and technology, perfect understanding of its various cross sections in the wide range of energy is indispensable. Scarcity of experimental data particularly in high energy makes theoretical evaluation essential. In the present work, different neutron interaction cross sections of 27Al in the energy range 0.1–200 MeV have been evaluated by TALYS 1.9. The reaction grid, outgoing light particle production and probable production routes are also analyzed. The present evaluations are compared with the available experimental and evaluated nuclear data: ENDF/B-VIII, JENDL-4.0, etc. This is generally in good agreement except 0.7–6 MeV of projectile energies. In this energy range, diffuseness and geometrical parameters are adjusted to overcome the disagreement. In the lowerenergy region, mainly elastic scattering is observed. Shape of non-elastic curve is well produced; however, there is small energy shift between evaluated and experimental data.

149Tb, 152Tb, 155Tb and 161Tb can cover all the modalities of diagnostic and therapeutic purposes of nuclear medicine. The production cross sections and yields of radiotheragnostics terbium from x+152,154,155,156,157,158,160Gd reactions in the energy range 0.001 to 200 MeV are evaluated using TALYS1.9. Some p,d,he3-induced reactions show high yields to produce 149Tb while several p,d,t-induced reactions show larger yields to produce 152Tb. For 155Tb productions, number of p,t-induced reactions have higher production yields. To produce 161Tb, one deuteron and one triton induced reaction show bigger production yields. These calculations are compared with EMPIRE 3.2.2 and TENDL-2017 data for prospective reactions.

58Ni(n, p)58Co, 58Ni(n, 2p)57Fe, 58Ni(n, d)57Co, 58Ni(n, t)56Co and 58Ni(n, a)55Fe reactions are studied using different NLD models from threshold to 20 MeV. Five phenomenological and two microscopic NLD are employed using TALYS 1.9 and EMPIRE 3.2.2 nuclear reaction codes for theoretical calculations. Experimental data taken from EXFOR data library were compared with these. Statistical factors H, R and D have been used to identify the best fitted model. Level density parameters have also been adjusted for further fine-tuning with experimental data. CTFG model is appeared to be a good theoretical fabricator for the neutron-induced 58Ni reaction with newly adjusted level density parameters.

56Fe(n,p)56Mn, 55Mn(n,p)55Cr, 52Cr(n,p)52V, 56Fe(n, α)53Cr, 55Mn(n, α)52V and 52Cr(n, α)49Ti reactions are evaluated using four phenomenological nuclear level density models from reaction threshold to 20 MeV. The calculated data is compared with the experimental nuclear reaction data from EXFOR database. Statistical factors H, D and R are computed to identify the best fit. Level density parameters are adjusted for further improvement of the fitting. Back shifted Farmi-gas model gives a resemblance of neutron-induced 56Fe, 55Mn and constant temperature Fermi-gas model gives a closeness for 52Cr reaction with our new parameter values.

Ship-breaking yards in the world mostly reside along the coastal areas which possess diverse elemental contents due to the presence of heavy minerals. So to explain the heavy elemental enrichment of ship-breaking sites in terms of only anthropogenic contribution is insufficient. While studying elemental distribution of ship-breaking sites, choosing appropriate control sample is vital. To evaluate the elemental distribution in ship-breaking yards of Bangladesh and in an adjacent island (Sandwip), soil samples from each site and some heavy minerals have been analyzed for Na, K, Sc, Cr, Fe, Co, As, Sb, Cs, La, Ce, Sm, Hf and Th abundances by neutron activation analysis. For assessing elemental distribution, pollution load index (PLI), geo-accumulation index and inter-element correlation study were performed. Co-related variation of Cr and Fe (r = 0.651) and chemical compositions of heavy minerals invoke that a significant portion of elemental enrichment in ship-breaking yards seems to have mineralogical origin while the enrichments of As, Sb and Cs (mean abundances: 11.3 ± 3.9, 5.66 ± 4.97 and 10.9 ± 6.6 ppm, respectively) are solely originated from anthropogenic activities (e.g., ship-breaking). On the other hand, elemental distribution of Sandwip (which is sometimes used as control sample) seems to be unaffected by the mainland ship-breaking activities and possesses crustal origin, though a minute fractionation of heavy metals is observed within the east (PLI: 0.84 ± 0.05) and west (PLI: 0.52 ± 0.04) side of the island. For the first time, this study reveals the mineralogical contribution of heavy elements in ship-breaking site and will be decisive for choosing proper elemental abundances of control site.

INVITED TALK

Invited Talk

The purpose of the present study is to assess the activity concentration of radionuclides in tea samples which were cultivated in Chitttagong region in Bangladesh. Total thirteen (13) tea samples were collected from different tea garden of Fatickchari, Rangunia and Banshkhali upozilla in Chittagong. The activity concentrations of 238U, 232Th, 40K and 137Cs in thirteen tea samples were measured, using a gamma spectrometry system with multichannel analyzer. The observed activity concentrations of 238U found in tea samples varied from 2.4 ± 0.4 Bq.kg-1 to 18.93 ± 1.72 Bq.kg-1 with mean concentration 5.34 ± 0.38 Bq.kg-1. The observed activity concentration of 232Th found in the tea sample varied 1.4 ± 0.56 Bq.kg-1 to 27.22 ± 3.65 Bq.kg-1 with mean concentration 10.07± 0.83 Bq.kg-1. The 40K activity in these tea samples varied from 151 ± 18.72 Bq.kg-1 to 1243 ± 83.91 Bq.kg-1 with mean concentration 430 ± 35.5 Bq.kg-1. No 137Cs activity was detected at any of the samples in the whole study area. The calculated values of Radium equivalent activity (Raeq) and the internal hazard index (Hin) for the tea samples are lower than the international permissible value of unity UNSCEAR (2000). It was concluded that the activity level of tea samples in the present study was non-threatening to public health.

Elsevier

Vol. 40

Vol. 40

Vol. 40

Vol. 4(4); Corpus ID: 208304018

ISSN: 2574-1241, Vol. 12, Issue 1, 2018

Invited Talk

Vol. 39

Vol. 65(2)

Vol. 29(1)

Vol. 162(4)

Vol. 37(1)

Vol. 12(9)

Vol. 25(1)

The research work has been aimed to assess the radiological and chemical threat caused due to urban and industrial wastage drainage to the inhabitants of the Chittagong city in Bangladesh. For finding the chemical effects along with the measurement of radiological threat, the physiochemical characteristics (temperature, pH value and oxidation-reduction potential) of the sediment samples have been analysed. The activity concentrations of naturally occurring radionuclides (238)U, (232)Th, (226)Ra and (40)K in the investigated samples have been found to be higher than those of the world average values. The artificial radionuclide (137)Cs in the samples studied has not been detected. The mean value of the radium equivalent activity and outdoor exposure rate in the study region have been found to be 240.94 ± 23.12 Bq kg(-1) and 115.82 ± 10.81 nGy h(-1), respectively. The radiation doses have been measured directly by employing beta-gamma survey meter (model: LUDLUM 44-9) from where the samples have been collected. The average values of the radiological parameters have been calculated from the activity concentrations of the radionuclides mentioned in the sediment samples found to be higher than those of the corresponding world average values.

Vol. 14(1)

Vol. 15(2)

Vol. 153(3)

Vol. 24(1)

The activity concentrations of naturally occurring and anthropogenic radionuclides in soil, grass and plant were measured in this work with an aim to determine the transfer factors of radionuclides from soil to grass and plant collected from Chittagong city in Bangladesh. The average activity concentrations of 226Ra, 232Th, 228Th, 40K and 137Cs in soil were found to be 22.13 ± 2.30, 38.47 ± 2.72, 50.47 ± 4.75, 451.90 ± 24.89 and 2.41 ± 0.18 Bq kg–1 respectively while in grass, their values were 1.26 ± 0.11, 3.66 ± 0.31, 7.02 ± 0.49, 134.95 ± 3.68 and 0.17 ± 0.02 Bq kg–1 respectively. In branches of the plant, the concentration values of these radionuclides are higher than those for leaves. For soil to grass, the transfer factor values were found to be 0.056, 0.089, 0.137, 0.275 and 0.054 respectively for 226Ra, 232Th, 228Th, 40K and 137Cs. For plant, soil to branch transfer factor values (0.062, 0.098, 0.136, 0.274 and 0.064 respectively for 226Ra, 232Th, 228Th, 40K and 137Cs) are higher than those for soil to leaves (0.054, 0.088, 0.127, 0.266 and 0.061 respectively).

Vol. 35

Vol. 35

Vol. 35

Neutron total and differential elastic scattering cross-sections for ^{55}Mn nucleus was calculated from different global spherical optical potential (SOP) sets for different neutron energies ranging from 0.2 MeV to 22 MeV using the well known computer program SCAT-2 on an IBM PC-AT. In addition, the angular distributions of elastically scattered neutrons at different neutron energies were calculated. The results were compared with those of the experimental data obtained from the EXFOR data file of NEA data bank. The best-fit potential parameter was thereby selected. It was observed that the best fit to the experimental values of the total cross-sections are obtained by SOP parameters of Kawai for ^{55}Mn. Furthermore, the variations of the total cross-sections as a function of real potential depth V_0 and real radius parameter r_0 were calculated to observe the sensitivity of these parameters towards the cross-sections.

Vol. 34

Vol. 34(2)

Heavy metals can have a serious impact if released into the environment even in trace quantities (Lin et al., 2005). These can enter into the food chain from aquatic and agricultural ecosystems and threaten human health indirectly (Lin et al., 2004). Dhalai Beel produces rice with DEPZ (Dhaka Export Processing Zone) effluent fed water. A field experiment was carried out to investigate the uptake of heavy metals by paddy crop using Thermal Neutron Activation Analysis (TNAA). Rice plants were divided into root, stem, leaf, husk and unpolished rice grain. The distribution of heavy metals in the different parts was investigated. The order of average contents of metals in rice was Zn > Rb > Se > Sc > Cr >Cs. The concentrations were Se 1.92–7.78 ppm, Cr BDL (Below Detection Limit) - 0.74 ppm, Sc 0.01–0.04 ppm, Rb 2.25–16.1 ppm, Fe–BDL, Zn 62.7–102.5 ppm and Co–BDL. Highest TF (Transfer Factor) value is obtained for Fe which is 0.24 and the lowest TF value is for Sc which is 0.02. The concentrations are within acceptable limits.

Vol. 44(4)

Vol. 32(1)

Vol. 40(2)

Vol. 2(1)

Vol. 6(1-2)