NaI Scintillation Research Articles

Variation of Secondary Gamma Radiation Flux during Closest Approach of Mars towards Earth, Mars at Opposition and Transit of Moon across Different Constellations and Planets in the Month of October, 2020 at Udaipur, India

Abstract: The experimental studies of closest approach of Mars towards Earth on October 6 & 7, 2020, Mars at opposition on October 13, 2020 and transit of Moon across different constellations and planets at Udaipur (270 43’ 12.00” N, 750 28’ 48.01” E), Rajasthan, India were conducted in the month of October, 2020 using a ground-based NaI (Tl) scintillation detector. For the closest approach of Mars, the data files were stored in computer for a half-hour duration from 20.30 IST to 1.00 IST on the dates of October 6 & 7, 2020, for Mars at opposition data files stored in computer for a half-hour duration from 18.00 IST to 20.00 IST on the date of October 13, 2020 and for Moon in the constellation experimental study the data files were stored in computer for a half-hour duration for the time 18.30 IST – 19.00 IST in the month of October, 2020 dated 19, 21, 22, 23, 25, 27, 28 and 29 at Udaipur (270 43’ 12.00” N, 750 28’ 48.01” E), Rajasthan, India, using a ground-based NaI (Tl) scintillation detector. For these experimental studies, the calibration of the scintillation detector was 2 keV per channel using a standard Cs137 source. Therefore, we detected the secondary radiation flux in the energy range from 2 keV to 2 MeV. Analyzed data of closest approach of Mars revealed a significant enhancement of secondary gamma-radiation flux (SGR) of about 4.5% on closest approach of Mars towards Earth at time 00.00 IST -00.30 IST (October 7) in comparison to the time 20.30 IST -21.00 IST (October 6). We interpret that such enhancement of SGR flux is on the basis of closest approach of Mars towards Earth, reflection of solar radiation from Mars towards Earth and gravitational lensing effect produced by Mars. For Mars at opposition, the analyzed data revealed a significant enhancement of secondary gamma-radiation flux (SGR) of about 1.7% in between times 19.00 IST – 19.30 IST. We interpret such enhancement of SGR flux on the basis of Mars at opposition, combined gravitational pull due to planet Mars, planet Earth and the Sun and gravitational lensing by Mars and for transit of Moon, the analyzed data revealed a significant variation of secondary gamma radiation flux (SGR) in the month of October. We interpret such variation of SGR flux on the basis of transit of Moon across different constellations and planets in the month of October. Keywords: Cosmic radiation, Reflection of solar radiation, Secondary gamma radiation, Closest approach of Mars, Mars at opposition, Combined gravitational pull and gravitational lensing effect by Mars, Transit of Moon across different constellations and planets.

Radiological Risk Parameters of the Phosphorite Deposits, Gebel Qulu El Sabaya: Natural Radioactivity and Geochemical Characteristics

This study investigates the distribution of natural radioactivity and geological, geochemical, and environmental risk assessments of phosphorite deposits to determine their suitability for international applications (such as phosphoric acid and phosphatic fertilizers). The examined Late Cretaceous phosphorite deposits belong to the Duwi Formation, which is well exposed on the southern scarp boundary at the central part of Abu Tartur Plateau, Gebel Qulu El Sabaya, East Dakhla Oasis. This formation is classified into lower phosphorite, middle shale, and upper phosphorite members. The lower phosphorite ranges in thickness from 2 to 3.5 m and mainly comprises apatite (possibly francolite), dolomite, calcite, quartz, hematite, anhydrite, and kaolinite. They contain an average concentration of CaO (38.35 wt.%), P2O5 (24.92 wt.%), SiO2 (7.19 wt.%), Fe2O3 (4.18 wt.%), MgO (3.99 wt.%), F (1.59 wt.%), Al2O3 (1.84 wt.%), Na2O (1.33 wt.%), and K2O (0.22 wt.%). Natural radioactivity and radiological parameters were investigated for fifteen samples of phosphorites using a NaI (Tl) scintillation detector. Absorbed dose rates, outdoor and indoor annual effective dose, radium equivalent activity, external and internal hazard, and excess cancer risk values are higher than the recommended levels, reflecting that exposure to these deposits for a long time may lead to health risks to human organs.

Experimental and theoretical investigation on physical, structure and protection features of TeO2–B2O3 glass doped with PbO in terms of gamma, neutron, proton and alpha particles

Glass series of composition 70TeO2- (30-x)B2O3- xPbO (where x = 2, 6, 10, 14 and 20 mol%) is prepared using melt-quenching technique. The glass structure was investigated by X-ray diffraction (XRD). Manufactured glass density, molar volume and Fourier transform infrared spectroscopy (FTIR) were measured. Shielding parameters against gamma-rays including, linear attenuation coefficient (μ), mass attenuation coefficients (μm), half-value layer (HVL) and mean free path (λ) were measured experimentally at energies of 0.664, 1.177 and 1.334 MeV using Cs137 and Co60 point sources and NaI(TL) scintillation detector. The measured parameters were compared with those calculated using XCOM program with a good agreement between them. To fully comprehend the shielding efficiency of the prepared glasses, several shielding parameters including, μm, HVL, effective atomic number (Zeff), electron density (Nel), equivalent atomic number (Zeq), exposure and energy absorption buildup factors (EBF & EABF), radiation protection efficiency (RPE) and kerma relative to air (Ka), were evaluated in the photon energy range 0.015–15 MeV and compared with some materials that commonly used as gamma-ray shielding. The findings demonstrate the viability of employing the current glass composition as an effective agent for gamma-ray shielding and fully protection (100%) for x-ray. The macroscopic effective removal cross section (ΣR) of the prepared glasses were calculated and compared with those of frequently used neutron shielding materials. Finally, the mass stopping power (MSP) and projected range (PR) values of proton (H1) and alpha particles (He+2) have been evaluated in the energy range 0.01–15 MeV. The results show that, increasing PbO content improves shielding characteristics. Among the examined samples, the S5 glass sample was found to be superior in terms of photon, neutron, proton and alpha particles protection. These results indicate that, the prepared glass samples are highly appropriate nuclear shielding material that can be used in many applications.

Effect of lead nanoparticles on the radiation shielding characteristics of carbon fiber/epoxy composites

Materials with shielding capabilities against gamma radiation are important for nowadays applications in order to alleviate radiation damage. This study investigates the shielding characteristics of carbon fiber/epoxy composites incorporating lead nanoparticles (Pb-NP) of variable weight fractions. The composites in this experimental study are prepared using the hand-layup vacuum bagging process at room temperature. Mass attenuation coefficients are calculated for composites with variable Pb-NP weight fractions based on radiation intensity measurements taken using NaI (Tl) scintillation detector. The results show that adding small fractions of lead nanoparticles to the matrix phase of the composite material leads to improving its shielding properties, including their linear attenuation coefficient, mass attenuation coefficient and the Half-Value Layer (HVL). The results also show that mass attenuation coefficients of composite material with added Pb-NPs are higher than those of pure lead. For validation purposes, the experimental results are compared to computational results obtained using MCNP5 code for the same weight fractions of Pb-NPs. The two sets of results were found to be in good agreement with a maximum relative error of ∼16%.

A closer look at the efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors using MCNPX for various types of nuclear investigations

The nuclear spectroscopy method has long been used for advanced studies on nuclear physics. In order to decrease costs and increase the efficiency of nuclear radiation investigations, quick and efficient solutions are required. The purpose of this research was to calculate the whole energy peak efficiency values for a range of gamma-ray energies, from 30.973 keV to 1408 keV, at various source-detector distances using the MCNPX Monte Carlo code, which is extensively used in nuclear medicine, industry, and scientific research. As a result, the modeled detectors' full-energy peak efficiencies were calculated and compared to both experimental data and Monte Carlo simulations. Experiment results and prior studies using Monte Carlo simulations were found to be very consistent with these results. The counting efficiency against source-detector distance is then calculated using the modeled detectors. The data we have show that LaBr3(Ce) has outstanding detection properties. This study’s findings might be used to improve the design of detectors for use in wide range of high-tech gamma spectroscopy and nuclear research applications.

Radiological mapping of tin mining areas in Doguwa, Kano State, Nigeria

This paper presents an extensive radiological mapping of the Doguwa tin mining areas of Kano, Nigeria, where uranium has been found in quantities for commercial mining. The goal of this study is to provide detailed radiological information that could be used as a reference in monitoring any future environmental changes that may result from other natural or artificial activities in the area. A total of 701 gamma dose rate in situ measurements were taken covering the study area using a portable NaI (Ti) scintillation detector (identiFINDER® 2). The measured terrestrial gamma dose rate varied between 38 and 958 nGy/hr with a mean value of 202 nGy/hr which is 3 times higher than the reported world average value of 59 nGy/hr by the United Nations Scientific Committee on the Effect of Atomic Radiation. The results varied significantly in accordance to the magnitude of the mining activities from one location to another. A radiological map of the study area was plotted using an ArcGIS software. The calculated values of the mean indoor, outdoor annual effective dose, and excess life cancer risk for the adult members of the public in the study area are 1 mSv/y, 0.25 mSv/y and 4.38 × 10−3 respectively. The findings in this study could be used for a proper radiation protection plan for the area.

Estimating the influence of various factors on the uncertainty of light collection simulation in scintillators

The paper is dedicated to the evaluation of statistical uncertainty of simulating the process of light transfer in NaI (Tl) and BGO scintillators by Monte Carlo method. The DETECT2000 program with a unified surface model was used. The process of light transfer (“fate”) by light photons was traced from the moment of appearance in the scintillator to the moment of passing through its exit window. The light collection coefficient was determined as the ratio of the number of photons that passed through the exit window to a given number of emitted photons. Different values of the number of emitted photons, optical transparency coefficients and fractions of the surface diffuse reflection were set. Multiple repetitions of the simulation process for a different set of properties made it possible to evaluate the precision and type A uncertainty of simulating the light collection coefficient for all possible options. It is shown that the uncertainty decreases when the statistics of the emitted photons is increased, and increases when the transparency and diffuse reflection fraction are decreased.

Distribution of Radionuclides and Radiological Health Assessment in Seih-Sidri Area, Southwestern Sinai.

The current contribution goal is to measure the distribution of the radionuclide within the exposed rock units of southwestern Sinai, Seih-Sidri area, and assess the radiological risk. Gneisses, older granites, younger gabbro, younger granites, and post granitic dikes (pegmatites) are the main rock units copout in the target area. Radioactivity, as well as radiological implications, were investigated for forty-three samples from gneisses (seven hornblende biotite gneiss and seven biotite gneiss), older granites (fourteen samples), and younger granites (fifteen samples of syenogranites) using NaI (Tl) scintillation detector. External and internal hazard index (Hex, Hin), internal and external level indices (Iα, Iγ), absorbed dose rates in the air (D), the annual effective dose equivalent (AED), radium equivalent activity (Raeq), annual gonadal dose (AGDE), excess lifetime cancer risk (ELCR), and the value of Upper Continental Core 232Th/238U mass fractions were determined from the obtained values of 238U, 232Th and 40K for the examined rocks of Seih-Sidri area. The average 238U mg/kg in hornblende biotite gneiss and biotite gneiss, older granites, and syenogranites is 2.3, 2.1, 2.7, and 8.4 mg/kg, respectively, reflecting a relatively higher concentration of uranium content in syenogranites. The results suggest that using these materials may pose risks to one’s radiological health.

LONG-TERM AFTERGLOW OF SOLID SCINTILLATORS.

Most of scintillators used for radiation detection exhibit afterglow, which is emission of light with longer decay times than that of main light pulse. High signal from afterglow has usually negative influence on detection parameters, e.g. for energy resolution in spectrometry measurements. The paper deals with long-term afterglow of some types of scintillators, which is more significant in the case of integral measurement when current in the photodetector is measured. The range of studied decay times was in the order of tens of seconds to days. Seven types of scintillators were measured: BGO, CaF2(Eu), CdWO4, CsI(Tl), LiI(Eu), NaI(Tl) and plastic scintillator. Excitation of scintillators was made using a UV lamp. After UV irradiation, a scintillator was inserted to scintillation detection unit and the anode current of photomultiplier tube was measured with a picoammeter. As results, CaF2(Eu) and plastic scintillator have relatively low long-term afterglow signal compared with other measured scintillators.

Development of 4πβ(LS)-γ digital coincidence counting system at NIM

A new 4πβ(LS)-γ digital coincidence counting (DCC) system has been developed at NIM. The system equipped with a triple-to-double coincidence ratio (TDCR) counter in the β-channel and a NaI(Tl) scintillation detector in the γ-channel. A dedicated DCC software was designed for off-line implementation of 4πβ(LS)-γ coincidence counting method. The software consists of three modules: software-based circuits module, dead-time and resolving-time correction module and efficiency extrapolation module, respectively. The performance of the newly developed 4πβ(LS)-γ DCC system was demonstrated by a comparison measurement of Co-60 solution with the conventional 4πβ(PC)-γ DCC system.

Thermal Neutron Detection in Mixed Neutron-Gamma Fields With Common NaI(Tl) Detectors

NaI(Tl) scintillators can detect thermal neutrons with surprising efficiency, even in the presence of ambient gamma radiation. This is due to a peculiarity of the <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">128</sup> I level scheme. Deexcitation cascades following neutron captures in <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">127</sup> I, a main constituent of NaI with quite large neutron capture cross section, unexpectedly often involve the 167.4 keV state of <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">128</sup> I with 175 ns half-life, which feeds another isomeric level at 137.9 keV having a half-life of 845 ns. The 29.5 keV transition between both levels, as well as the subsequent deexcitation sequence to ground state comprising 137.9 keV sum energy, are almost certainly absorbed in the crystal. Signals including three scintillation pulses within few microseconds, the first one caused by a prompt part of the cascade, the second and third one disclosing 30 and 138 keV energy depositions and characteristic delays, are clearly related to such neutron captures. Double-pulse sequences comprising only the primary pulse and a delayed 138 keV signal are also distinctive but more prone to load-dependent background by random pulse pileups. This article demonstrates neutron detection with a Ø2” <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$\times2$ </tex-math></inline-formula> ” NaI(Tl) scintillation detector by finding and analyzing such double- and triple-pulse sequences in digitized detector signals. It quantifies effect and background rates as a function of the detector load ranging up to 30 kcps. Complementary measurements with a <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">6</sup> Li codoped Ø2” <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$\times2$ </tex-math></inline-formula> ” NaI(Tl) (NaIL) scintillator allow relating the neutron detection yield by delayed-coincidence counting to the <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">6</sup> Li capture rate in the same crystal and thus to evaluate prospects and limits of this technique.

Radiation attenuation properties of novel glass system using experimental and Geant4 simulation

The purpose of this study is to estimate the radiation shielding capacities of glass systems with the system of 45 SiO2 – 15 CaO – (40-x) BaO – (x) ZnO (where x = 0,10,20, 30, and 40 wt%). The mass attenuation coefficients, μ/ρ of these glasses have been calculated by using XCOM software and Geant4 simulation toolkit tool in the energy range of 0.0595 MeV–1.410 MeV. The experimental data have been carried out using a narrow beam using the NaI(Tl) scintillation detector at the energies of (59.52 KeV) 241Am, (661.66 keV) 137Cs, (1173.23, 1332.50 keV) 60Co, 152Eu(121.78, 244.69, 344.28, 964.13, 1408.1 KeV). The MAC calculated results were compared with the experimental values. There have been good agreements noticed. The other attenuation parameters were calculated such as the linear attenuation coefficient (μ), half value layer (HVL), mean free path (MFP) and the effective atomic number (Zeff). The attenuation results of this glass system were compared with some recently published commercial glasses, and the results showed that this glass system is important in the radiation protection field.

Measurement of the angular correlation between the two gamma rays emitted in the radioactive decays of a 60Co source with two NaI(Tl) scintillators

We implemented a didactic experiment to study the angular correlation between the two gamma rays emitted in typical 60Co radioactive decays. We used two NaI(Tl) scintillators, already available in our laboratory, and a low-activity 60Co source. The detectors were mounted on two rails, with the source at their center. The first rail was fixed, while the second could be rotated around the source. We performed several measurements by changing the angle between the two scintillators in the range from 90° to 180°. Dedicated background runs were also performed, removing the source from the experimental setup. We found that the signal rate increases with the angular separation between the two scintillators, with small discrepancies from the theoretical expectations.

Transit of the Sun across Constellations Libra, Virgo and Variation of Secondary Gamma Radiation Flux in the Months of November 2018 and September 2019, Respectively at Udaipur, India

Abstract: We reported a significant variation of secondary gamma radiation flux (SGR) in month November 2018 and month September 2019 at Udaipur during transit of Sun across constellations. The data was collected as a function of time using a ground-based NaI (Tl) scintillation detector. We interpret such variation of SGR flux on the basis of combined gravitational pulling along with gravitational lensing effect on background radiation by the Sun, constellations and radiation from constellations. Keywords: Cosmic radiation, Sun, Solar radiation, Secondary gamma radiation, Libra constellation, Virgo constellation, Planets, Gravitational pulling, Gravitational lensing.

Enhancement of Secondary Gamma Radiation Flux Energies in the Energy Region from 1400 Kev to 1500 Kev during Lunar Eclipse on June 16, 2011 at Udaipur, India

Abstract: The lunar eclipse at Udaipur (270 43’ 12.00” N, 750 28’ 48.01” E), India was experimentally observed on June 16, 2011 using ground-based NaI (Tl) scintillation detector. Cadences of data were collected at intervals of half an hour. The analyzed data revealed a significant enhancement in the energy region from 1400 keV to 1500 keV of secondary gamma radiation flux (SGRF) on comparison to pre- and after lunar eclipse days. On June 16, we observed additional peaks in the energy spectrum of SGR flux in the energy region extending from 1461.010 keV to 1472.536 keV during the progress of lunar eclipse. We interpret such enhancement of SGR flux energies on the basis of combined phenomenon of gravitational lensing effect of Sun and Earth as well as the Sun’s magnetic field and the interplanetary magnetic field. Due to such combined effect, primary cosmic and solar radiations bend and may cause strong hitting on the less air surface of the Moon, resulting into emission of secondary particle flux mostly gamma radiation, high energy photo electrons, hard X -radiation, muons, protons and neutrons which may be regarded as back scattering from the Moon surface. Energy of backscattered secondary flux is large enough that it gives such enhancement in the energy region from 1400 keV to 1500 keV during lunar eclipse observation. Also, due to combined gravitational effect, cosmic radiation bent and impinged deep inside the atmosphere of Earth, producing a large shower of secondary radiation particles. These collective effects may give such enhancement of secondary gamma radiation flux energies. Keywords: Lunar eclipse, Solar magnetic field, Interplanetary magnetic field, Gravitational lensing, Bending of primary cosmic and solar radiations.

Decrement of Secondary Gamma Radiation Flux during Solar Eclipses on January 4, 2011 and December 26, 2019 at Udaipur, India

Abstract: The solar eclipses at Udaipur (270 43’ 12.00”N, 750 28’ 48.01”E), India were experimentally observed on January 4, 2011 and December 26, 2019 using a ground-based NaI (Tl) scintillation detector. For the solar eclipse on January 4, 2011, the data files were stored in a computer for a thirty-minute duration from 14.30 IST to 15.00 IST on pre-eclipse normal days as well as on post-eclipse normal days and also on partial eclipse day (January 4, 2011). For solar eclipse on December 26, 2019, cadences of data were collected for three hours from 8 AM to 11 AM on pre-eclipse normal days as well as on post-eclipse normal days and also on eclipse day (December 26, 2019). The analyzed data revealed significant decrement of secondary gamma radiation flux (SGR) on solar eclipse day (January 4, 2011) of about 10 % and on solar eclipse day (December 26, 2019) of about 17 % in the counts of SGR flux on comparison to average counts of normal days. We interpret such decrement of SGR flux on the basis of obstruction effect produced by the Moon during solar eclipses. Keywords: Solar eclipse, Cosmic radiation, Solar radiation, Secondary gamma radiation, Obstruction effect by the Moon.

Radioactivity Levels in Water Samples of Tigris River in Baghdad City, Iraq

The natural radioactivity levels in water samples along the Tigris river (one of the major rivers of the world) within Baghdad city were investigated to determine and evaluate the radioactivity risks in the water of the river. The specific activity of the radionuclides (238U, 232Th, 40K, and 137Cs) for thirty different water samples from Tigris river within Baghdad city were measured using gamma-ray spectrometer, employing a NaI(Tl) scintillation detector. The results showed that the average value of the specific activity for 238U, 232Th, 40K, and 137Cs were (24.20, 16.70, 329.22, and 19.40) Bq/l, respectively. The calculated average annual effective doses for different age groups were found to be (3.80, 6.57, and 5.59) mSv/y for infants, children, and adults, respectively, which are much higher than the globally allowed annual limits of the dose (0.26, 0.2 and 0.1) mSv/y for infants, children and adults, respectively, and it has harmful effects on health.

Detection efficiency evaluation for low energy of a NaI(Tl) scintillation detector

To improve the characterization of the detection efficiency of a NaI(Tl) scintillation detector in the low energy range, measurements and Monte Carlo simulations were performed with a certified reference material (CRM) and disk sources. The detection efficiency as modeled. In the MCNP simulation, the detection efficiency dropped as expected at 33.17 keV. The X-ray escape correction factors of a 204Tl disk source and MCNP simulations were compared, a factor of the 204Tl was similar. Moreover, Correcting the X-ray escape and using fewer sources than the CRM resulted in better detection efficiency for the NaI(Tl) detector in the low energy range.

Experimental and Simulated Spectral Gamma-Ray Response of a NaI(Tl) Scintillation Detector used in Airborne Gamma-Ray Spectrometry

Abstract. The objective of this work is to simulate the spectral gamma-ray response of NaI(Tl) scintillation detectors for airborne gamma-ray spectrometry (AGRS) using the state-of-the-art multi-purpose Monte Carlo code FLUKA. The study is based on a commercial airborne gamma-ray spectrometry detector system with four individual NaI(Tl) scintillation crystals and a total volume of 16.8 L. To validate the developed model, radiation measurements were conducted using 57Co, 60Co, 88Y, 109Cd, 133Ba, 137Cs and 152Eu calibration point sources with known activities and source-detector geometries under laboratory conditions. In addition, empirical calibration and resolution functions were derived from these measurements combined with additional radiation measurements adopting natural uranium, thorium and potassium volume sources. The simulation results show superior accuracy and precision compared to previous AGRS simulation models with a median relative spectral error &lt; 10 % for most of the radiation sources. Moreover, the implementation of a lower level discriminator model and detailed modelling of the laboratory result in a significant improvement in model accuracy for spectral energies &lt; 100 keV compared to previous studies. Yet thorough statistical analysis incorporating statistical and systematic uncertainty estimates revealed statistically significant deviations between the simulated and measured spectra in the spectral region around the Compton edge, which could be attributed to the scintillator non-proportionality. These findings imply that the linear energy deposition model applied in this and previously developed AGRS simulation models should be revised and considered to be replaced by more accurate non-proportional models.

Radiation Interaction Characteristics of Solutions of La(NO3)3.6H2O and Sm(NO3)3.6H2O in Acetone Using Compton Scattering Technique

This work deals with the evaluation of interaction cross sections, effective atomic number, and effective electron density at gamma photon energies, not available from standard radioisotopes. The Compton scattering technique is used to obtain the required gamma energies within a specific range of energies from 241.8 to 401.8 keV to perform the radiation measurements. Radiation interaction parameters of some inorganic compounds (high-Z rare-earth nitrate hexahydrate), namely, Lanthanum(III) nitrate hexahydrate [La(NO3)3.6H2O] and Samarium(III) nitrate hexahydrate [Sm(NO3)3.6H2O], soluble in low-Z organic solvent (acetone) are evaluated. Six scattering angles are chosen to obtain six (not available from standard radioisotopes) Compton scattered energies to perform narrow-beam transmission experiments. An NaI(Tl) scintillation detector is used to detect the transmitted flux from the different solutions in various proportions. Photon interaction parameters useful in vast basic and applied fields are evaluated. The present measured results, obtained from the Compton scattered technique, are found to be in good agreement with the computed values of radiation interaction parameters obtained from the WinXCom program. The present data on rare-earth solutions have definite scientific importance in nuclear and radiation physics and fill in the gap of nonavailability of such data for radiation workers at these specific energies.