Browsing by Author "Kavaz, Esra"

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Assessment on Gamma Radiation Shielding Properties of Molybdenum Doped Bricks
(Pergamon-elsevier Science Ltd, 2023) Oto, Berna; Kavaz, Esra; Durak, Halil; Madak, Zekiye
Gamma radiation permeability experiments were carried out by preparing a new type of brick mixture with Molybdenum (Mo, Z = 42) additives (0 (B0), 5 (B1), 10 (B2), 20 (B3), 30 (B4), 40 (B5), 50 (B6) %wt). The density of the bricks increased to 2.79 g/cm(3) with increasing Mo content. The bricks were exposed to gamma rays with 81, 276, 303, 356 and 383 keV photon energies emitted from Ba-133 radioactive source and the transmitted intensities were detected using the Canberra Ultra Ge detector. Gamma attenuation characteristics of the bricks were also calculated by mass attenuation coefficients, effective atomic numbers and electron densities using the EpiXS program as a function of gamma-ray energy. And also, the exposure and energy absorption buildup factors of bricks were determined at different mean-free paths and photon energies using EpiXS program. It was observed that as the density of the bricks increased, the radiation shielding properties also increased. The values of the mass attenuation coefficients at 81 keV for B0-B6 bricks were found to vary between 0.229 and 1.08 cm(2)/g. It was found that Z(eff) values were 13.3, 16.1, 17.4, 19.09, 22.5, 25.3 and 26.6 for B0, B1, B2, B3, B4, B5 and B6 samples at 81 keV, respectively. As can be seen from these results, B6 brick has the highest Z(eff) value. And also, the calculated results displayed that the lowest values of exposure buildup factors and energy absorption buildup factors are observed for the B6 brick. The B6 brick containing 50% Mo element has a higher mass attenuation coefficient and effective atomic number values than the other bricks. The values of exposure and energy absorption buildup factors of B6 brick were lower than the values of other investigated samples. The measured and calculated shielding values of the bricks were in close agreement. It has been seen that the shielding results of these new types of bricks, which are low in cost and easy to produce and use, are quite successful.
Effect of Addition of Molybdenum on Photon and Fast Neutron Radiation Shielding Properties in Ceramics
(Elsevier Sci Ltd, 2019) Oto, Berna; Kavaz, Esra; Durak, Halil; Aras, Aydin; Madak, Zekiye
In the present research, standard ceramic and Molybdenum (Mo) doped ceramics were fabricated to determine the shielding properties against gamma and fast neutron radiation. The ceramics were exposed to photons with 81, 276, 302, 356, 383 keV energies emitted from 3 Ci Ba-133 radioactive source and the photon intensities were detected by utilizing Ultra Ge detector. With the obtained results, the gamma shielding parameters; mass attenuation coefficients (mu(rho)), the mean free paths (mfp), half value layers (HVL), tenth value layers (TVL), effective atomic numbers (Z(eff))and effective electron densities (N-el) were obtained experimentally and compared to the theoretical outcomes computed by utilizing WinXCOM program. It was found that, S4 ceramic containing 30% Mo element has higher mu(rho) and Z(eff ) value and lower MFP, TVL and HVL values than the other ceramics. The EBF and EABF values of S4 ceramic were lower than the values of other investigated ceramics. Thus, it has been concluded that the use of Mo element in ceramic increases the gamma shielding property of the ceramics. When the ceramics were examined in terms of fast neutron shielding, no important difference was found between the ceramics.
Effective Atomic Numbers, Electron Densities and Gamma Rays Buildup Factors of Inorganic Metal Halide Cubic Perovskites Csbx3 (B = Sn, Ge; X = I, Br, Cl)
(Pergamon-elsevier Science Ltd, 2019) Oto, Berna; Gulebaglan, Sinem Erden; Madak, Zekiye; Kavaz, Esra
The present investigation has been undertaken to evaluate gamma radiation shielding effectiveness of inorganic metal halide cubic perovskites CsBX3 (B = Sn, Ge, Pb; X = I, Br, Cl). The values of mass attenuation coefficients (mu/rho) were computed at the energy range of 1.00 keV-100 GeV by WinXCom computer code. Thereupon, half value layer (HVL), the effective atomic number (Z(eff)) and electron density (N-el) are calculated by using mu/rho values. Besides, energy absorption buildup factor (EABF) and exposure buildup factor (EBF) of inorganic metal halide cubic perovskites have been determined using the Geometric Progression (G-P) fitting method at energies 0.015-15 MeV up to penetration depths of 40 mean free path (mfp). The examined shielding parameters are highest in low energy region and lowest in the middle energy region. The results were discussed in relation to the contents of the samples. The lead-containing compounds are more efficient than the other compounds for shielding gamma radiations. Other perovskites (without lead) also have the ability to absorb radiation better than many other shielding materials currently used. Thus, the studied compounds may be effective in the production of novel shielding materials.
Evaluation of Gamma-Ray Attenuation Properties of Lithium Borate Glasses Doped With Barite, Limonite and Serpentine
(Walter de Gruyter Gmbh, 2018) Yorgun, Nergiz Yildiz; Kavaz, Esra; Oto, Berna; Akdemir, Fatma
The values of mass attenuation coefficient, the effective atomic number and the electron density of barite-doped, limonite-doped, serpentine-doped and undoped lithium borate glasses were obtained not only from experimental study using the narrow beam transmission method for 81, 121, 244, 276, 344, 383, 444 and 778 keV gamma energies with Hp-Ge detector, but also therotical work by WinXCom software (1 keV-10(5) MeV). From the obtained results, all glasses type mass attenuation coefficient values tend to decrease under the condition of increasing energy by means of varied interaction mechanism in different energy regions. In addition, the effect of chemical composition on shielding properties was also investigated. It is inferred that doping element with high atomic number improves the gamma rays shielding properties of system. Among the investigated samples, barite-doped lithium borate glasses have highest value of mass attenuation, which makes barite-doped samples good candidates for artificial radiation application where visual detection is especially required.
An Experimental Study on Gamma Radiation Attenuation Effectiveness of Magnetite and Serpentine Doped Ceramics
(Pergamon-elsevier Science Ltd, 2024) Oto, Berna; Cakar, Nurtac; Kavaz, Esra; Madak, Zekiye
The present study aims to investigate the gamma-ray (gamma) and fast neutrons attenuation characteristics of magnetite and serpentine doped ceramics via theoretical and experimental. gamma radiation permeability experiments were carried out by preparing a new type of ceramics with magnetite (M) and serpentine (S) additives [0 (C), 10 (M1; S1), 20 (M2; S2), 30 (M3; S3), wt %]. The fabricated shields were exposed to gamma radiation with 81, 160, 223, 302, 356 and 383 keV energies emitted from (133)Barium radioisotope and the measured intensities were detected by Canberra Ultra Ge detector. The parameters such as mass attenuation coefficients (mu(rho)), effective atomic numbers (Z(eff)), electron densities (N-el), half-value thickness (Delta(0.5)) and mean free path (lambda) characterizing the gamma shielding properties of the materials were determined. All theoretical gamma shielding parameters were calculated by running the EpiXS program. And also, exposure (EBF) and energy absorption (EABF) buildup factor values of ceramics were determined at different mean-free paths and photon energies using the EpiXS program. And finally, the macroscopic removal cross-section values (Sigma(R)) for fast neutrons of ceramics were computed. It was found that the density of the ceramic sample increases with the addition of ore. The values of (mu(rho)) are found to depend on the concentration of ore in the ceramics. The mu(rho) values of M3 ceramic are the highest whereas the mu(rho) values of C ceramic are the lowest in all studied ceramics. The M3 has the lowest half-value thickness (Delta(0.5)) and mean free path (lambda) values compared to other studied ceramics. The values of Z(eff) and N-el change as S3
An Experimental Study on the Radiation Shielding Properties of New Type Ceramics Containing Limonite and Hematite Minerals
(Elsevier Science Sa, 2025) Oto, Berna; Kavaz, Esra; Madak, Zekiye; Cakar, Nurtac
In this study, the development and evaluation of new ceramic materials doped with limonite and hematite minerals in terms of their effectiveness in gamma ray and neutron shielding was investigated. The primary aim is to determine gamma-ray shielding parameters for these ceramics, using gamma photon energies emitted from the Barium-133 radioisotope at specific energy levels (81, 160, 223, 302, 356, and 383 keV). Measurements were conducted using a Canberra Ultra Ge detector to detect the intensities of radiations. The mass attenuation coefficient (mu p), half-value thickness (A0.5), mean free path (2) and effective atomic numbers (Zeff) were determined experimentally and theoretically. And, exposure (EBF) and energy absorption (EABF) buildup factor values of ceramics were determined at different mean free paths and photon energies using the EpiXS program. Intercalarily, fast neutron attenuation parameters (ER) of ceramics have also been calculated. The densities of the ceramics increased with the addition of limonite and hematite minerals, ranging from 2.61 g/cm3 to 3.12 g/cm3 as the limonite content increased from 0 wt% to 30 wt %. Similar density variations were observed with the addition of hematite. There is a direct proportional relationship between the density of the ceramics and their shielding effectiveness. The effective atomic numbers (Zeff) were ranked as C G H1 G H2 G H3 G L1 G L2 G L3, indicating that the shielding effectiveness improves with higher doping levels. The L3 ceramic (with 30 % limonite addition) sample exhibited the highest fast neutron removal cross-section values among the tested samples. The findings demonstrate that doping ceramics with limonite and hematite minerals enhances their
Gamma Photon Protection Properties of Some Cancer Drugs for Medical Applications
(Elsevier Science Bv, 2019) Yorgun, Nergiz Yildiz; Kavaz, Esra
Chemotherapy stops or slows down the growth and proliferation of cancer cells. Chemotherapy usually uses in combination with, surgery, radiotherapy or other treatments. Therefore, it is useful to calculate the photon interaction parameters to determine the energy accumulation and penetration in tissue due to the interaction of cancer drugs with radiation. In this work, the mass attenuation coefficient (mu/rho), half value layer (HVL) and effective atomic number (Z(eff)) of some cancer drugs (Tadocel, Fluro-5, Erbitux, Carboplatin, Temodal, Tamoxifen, Endoksan and Oxaliplatin) have determined experimentally at 13.81, 17.7, 26.34 and 59.54 keV photons emitted from Am-241-point source by using Si(Li) detector. Besides, we calculated theoretically the gamma-ray interaction parameters using the WinXCOM software program. Next to these, utilizing the GP fitting approach, exposure buildup factors (EBF) of the drugs determined up to 40 mfp in the energy range 0.015-15 MeV. Experimental and theoretical results have been found to be in harmony. Oxaliplatin and Carboplatin have larger mu and Z(eff) and lower HVL values than the other drugs under study. The smallest EBF values are observed for Endoksan, Oxaliplatin and Carboplatin for all of the penetration depths. Oxaliplatin, carboplatin and endoksan possess significantly good radiation absorbing effect.
Gamma Ray Buildup Factors of Lithium Borate Glasses Doped With Minerals
(Elsevier Science Sa, 2018) Kavaz, Esra; Yorgun, Nergiz Yildiz
Five parameters (G-P) fitting method was used to calculate the gamma ray energy absorption and exposure buildup factor values of barite-doped, limonite-doped, serpentine-doped and undoped lithium borate glass types for incident photon energy, between 0.015 MeV and 15 MeV, and penetration depths, 40 mean free path. It was observed that the buildup factor values vary with not only different incident gamma energy values, but also chemical composition of glass samples. According to our results, the barite and limonite doped glasses (B1, B2 and L2) have the lowest values of energy absorption and exposure buildup factors. Among the selected sample of glasses, the barite and limonite-doped glasses possessed superior gamma-ray shielding effectiveness due to their higher equivalent atomic number values and the lower energy absorption and exposure buildup factor values. In other words, the presence of highly equivalent atomic number minerals improves the gamma ray shielding characteristics of the lithium borate glasses. Moreover, EABF and EBF values were compared and discussed. (C) 2018 Elsevier B.V. All rights reserved.
The Impact of Co Addition on Neutron-Photon Protection Characteristics of Red and Yellow Clays-Based Bricks: an Experimental Study
(Pergamon-elsevier Science Ltd, 2022) Durak, Halil; Kavaz, Esra; Oto, Berna; Aras, Aydin
High strength and heat resistance properties of radiation shielding materials are among the most sought properties. Due to their mechanical and thermal properties, bricks can be a good alternative for radiation protection applications. In this respect, nuclear radiation attenuation parameters of seven brick samples containing different amounts of Cobalt metal (0, 5, 10, 20, 30, 40, 50 %wt) were examined in this study. Initially, SEM-EDX analysis of bricks were carried out to determine the elemental composition and structure of the bricks. Next, the bricks were exposed to gamma rays with 53.16, 79.61, 80.99, 276.39, 302.85, 356.01, 383.84 keV photon energies emitted from Barium-133 radioactive source and the transmitted photon intensities were detected by utilizing Ultra-Ge detector. Mass attenuation coefficient (MAC), effective atomic number (Z(eff)), Half Value Layer (HVL), Mean Free Path (MFP) and exposure buildup factors (EBF) values of bricks were determined by experimentally and EpiXS program. At 53.-383 MeV photon energy interval, it is found that the MAC values for S0-S6 brick samples range between 0.427 and 0.097 cm(2)/g and 1.130-0.0961 cm(2)/g. In addition, the neutron shielding features of the bricks under study were assessed by calculating effective removal cross section (Sigma(R) ). It is noticed that the Sigma(R) values of the samples gradually grow from 0.057 cm(-1) to 0.1392 cm(-1) with increasing Co addition. It has been concluded that rising the Co addition improves the gamma and neutron shielding capacity of the brick samples.
Improvement of Nuclear Photon and Neutron Shielding Performance of Tm2o3 and Dy2o3 Doped Ceramics: an Experimental Study
(Pergamon-elsevier Science Ltd, 2024) Madak, Zekiye; Oto, Berna; Kavaz, Esra; Cakar, Nurtac
In this study, 60KAlSi3O8+10Al2Si2O5(OH)4+(30-x)SiO2+xA2O3 (x = 0, 10, 20, 30 wt% and A = Tm, Dy) ceramics were produced by conventional method to determine their usability as shielding material against ionized gamma radiation. To investigate the ionized photon shielding properties of the fabricated materials, the photon intensities (I and I0) were experimentally measured at 81, 160, 223, 302, 356, and 383 keV energies emitted from 133Barium radioisotope, and then the mass attenuation coefficient (mu p), The linear attenuation coefficients (mu, cm-1), half-value thickness (A0.5), mean free path (A), effective atomic numbers (Zeff) and electron densities (Nel) were derived experimentally. The obtained results were benchmarked with the calculated values from the EpiXS program. Also equivalent absorbed dose (EAD) values for fast neutrons were measured using BF3 gas proportional neutron detector from the Canberra NP-100B series and a241Am/Be neutron source with a 10 mCi activity. In addition, fast neutron shielding parameters (ER) of ceramics were also computed theoretically. The density of the fabricated ceramics varied from 2.607 g/cm3 to 4.392 g/cm3 when the Tm2O3 was raised from 0 wt% to 30 wt%. Likewise, with the addition of Dy2O3 compound, the densities of ceramics varied between 2.607 g/cm3 to 4.152 g/cm3. It was found that nuclear radiation shielding properties evolved by adding Tm2O3 and Dy2O3 compounds in the present ceramic.
Improving the Performance of Nuclear Protection of Al2si2o5(oh)4-Kalsi3o8 With Cobalt Insertion: an Experimental Study
(Springer, 2020) Kavaz, Esra; Oto, Berna; Durak, Halil; Madak, Zekiye
In this study, nuclear radiation shielding features of Al2Si2O5(OH)(4)-KAlSi3O8-SiO(2)ceramic systems were explored by depending on cobalt (Co) insertion ratio (0, 5, 10, 20, 30 wt%). For this aim, five ceramic samples were produced and their elemental compositions were obtained with SEM-EDX analysis. Then, transmission measurements were achieved by using an ultra Ge detector and photons with 0.081-0.383 keV energy ranges. From the evaluated transmission spectra, mass attenuation coefficient (mu(rho)) values of five ceramics were obtained experimentally and compared with theoretical results. According to the outcomes, the increment of the Co insertion rises the mu(rho)values, whereas the half-value layer (HVL) value declines. It is also observed that effective atomic number (Z(eff)) values are raised, while effective electron density (N-el) is declined as Co additive increases in the ceramic sample. The geometric progression (GP) approach was utilized to estimate the energy absorption buildup factor (EABF) and exposure buildup factor (EBF) for the produced ceramic samples. EABFs and EBFs were obtained to be the smallest for 30% doped S5 sample according to the other ceramic samples. Lastly, the neutron attenuation ability of the ceramic samples was interpreted by finding the effective neutron cross sections (sigma(R)). It is noticed that the sigma(R)values are almost similar for all of the ceramics. As a result, the S5 sample is a skilled nominee for photon and neutron protection applications among the fabricated ceramic samples. Graphical abstract
The Interaction of Gamma Radiation With Drugs Used in Cholinergic Medications
(Taylor & Francis Ltd, 2020) Oto, Berna; Oto, Gokhan; Madak, Zekiye; Kavaz, Esra
Purpose: Pharmacological medications can reduce the radiation damage in the organism when applied in the stage before or after exposure to radiation. Cholinergic drugs are a category of pharmaceutical agents acting on the neurotransmitter acetylcholine, the primary neurotransmitter in the parasympathetic nervous system. In this investigation, some gamma radiation interaction parameters namely mass attenuation coefficients (mu(rho)), effective atomic number (Z(eff)) and electron densities (N-el) of 12 cholinergic system drugs have been calculated in the energy range 1 KeV-100 GeV. In addition, gamma-ray energy absorption (EABF) and exposure (EBF) of buildup factors have been computed using the five-parameter geometric progression (G-P) fitting formula for investigated drugs in the energy range 0.015-15 MeV, and for penetration depths up to 40 mean free path (mfp). Materials and methods: In order to perform these calculations, data obtained from WinXCom computer program were used. The computed mu(rho) values were then used to calculate the effective atomic numbers and electron density of the investigated drugs. To compute the buildup factors, the G-P fitting parameters were determined by the method of interpolation from the equivalent atomic number, 'Z(eq)' Results and Conclusions: It has been concluded that effective atomic number and electron density of malathion is bigger than the other drugs and the variations in values of Z(eff) and N-el for all drugs depend on chemical compositions and photon energy where the K-absorption edge of elements may affect the energy dependence of Z(eff) and N-el. It should also be noted that the buildup of photons is less in malathion and carbachol and is more in tabun and parathion compared with other drugs. Photon interaction parameters evaluated in the present study may be beneficial in radiation dosimetry and therapy.
Investigation of Gamma and Neutron Radiation Shielding Properties of Ceramics Produced Using Some Lanthanide Compounds
(2024) Madak, Zekiye; Oto, Berna; Kavaz, Esra
Herhangi bir radyasyon tehlikesine karşı alınabilecek birincil önlem zırhlamadır. Zırhlama, radyasyondan kaynaklı zararlı etkileri azaltmak için kullanılan bir önemli yöntemdir. Zırh malzemesi, bu amaç için üretilen koruyucu engellerdir. Bu koruyucu engeller üretilirken radyasyonun türü ve enerjisi dikkate alınmak zorundadır. Bunun nedeni, yüksek atom numarasına sahip element içeren malzemelerin yüksek enerjili fotonları zayıflatmak için kullanılması, düşük atom numaralı malzemelerin ise nötron parçacıklarını zayıflatmak için kullanılmasıdır. Zırh malzemesi üretiminde dikkat edilmesi gereken birkaç önemli noktalar vardır. Bunları şu şekilde sıralamak uygundur: i) zırh malzemesinin kolay üretimi; ii) doğaya zarar vermemelidir; iii) Maliyet ucuz olmalıdır. Bu üç önemli niteliğe sahip olan seramik malzemeler etkili zırh malzemeleri olarak kullanılmaktadır. Bu çalışmada, lantanit bileşikleri içeren farklı türdeki seramiklerin iyonlaştırıcı gama radyasyonuna karşı koruyucu malzeme olarak kullanılabilirliğini belirlemek amacıyla geleneksel yöntemler kullanılarak üretildi. Üretilen malzemelerin iyonize foton zırhlama özelliklerini araştırmak için, 133Ba radyoizotopundan yayılan 81, 160, 223, 302, 356 ve 383 keV enerjilerde foton yoğunlukları (I ve I0) deneysel olarak ölçüldü ve ardından kütle zayıflama katsayısı (µm), Doğrusal zayıflama katsayıları (μ, cm-1), yarı değer kalınlığı (HVL), ortalama serbest yol (MFP), etkili atom numaraları (Zetk) ve elektron yoğunlukları (Nel) deneysel olarak türetilmiştir. Elde edilen sonuçlar EpiXS programından hesaplanan değerlerle karşılaştırıldı. Ayrıca hızlı nötronlar için eşdeğer absorbe doz (EAD) değerleri, Canberra NP-100B serisinden BF3 gaz orantılı nötron dedektörü ve 10 mCi aktiviteye sahip 241Am/Be nötron kaynağı kullanılarak ölçüldü. Ayrıca seramiklerin hızlı nötron zırhlama parametreleri (ΣR) de teorik olarak hesaplanmıştır. Anahtar kelimeler: Lantanitli bileşikler, Radyasyon, Radyasyon zırhlama, Seramik
Investigation of Gamma Radiation Shielding Properties of Various Ores
(Pergamon-elsevier Science Ltd, 2015) Oto, Berna; Yildiz, Nergiz; Akdemir, Fatma; Kavaz, Esra
Mass attenuation coefficients (mu/p, cm(2)/g) for some pellet samples produced using barite, magnetite, limonite, hematite and serpentine ores at 81, 276, 302, 356, 383 key photons emitted from Ba-133 and 121, 244, 344, 444, 778 keV photons emitted from Eu-152 have been determined by using HPGe detector. Effective atomic numbers (Z(eff)) and electron densities (N-e) of the ores calculated in the selected energies.. The agreement of measured values of mu/p, Z(eff) and N-e with theoretical calculations is quite satisfactory. Mass attenuation coefficients were found to be highest for barite. The Z(eff) and N-e values for barite are maximum, for serpentine are minimum. Gamma ray energy absorption (EABF) and exposure buildup factors (EBF) were computed for ore samples using the five-parameter Geometric Progression (G-P) fitting method in the energy range 0.015-15 MeV for penetration depths up to 40 mean free path. Variations of EABF and EBF with incident photon energy and penetration depth were also investigated. It has been observed that among the selected ore samples, barite has lowest values for EABF and EBF in the intermediate energy region. Buildup of photons is more for serpentine. Exposure buildup factors (EBF) of given ores were compared with lead, steel-magnetite concrete (SM), concrete and bismuth borosilicate glass (BBS) with %20 mol Bi2O3. Barite is superior in terms of shielding properties among the other ore samples. The present study may be useful for radiation shielding applications. (C) 2015 Elsevier Ltd. All rights reserved.
Neutron Shielding Qualities and Gamma Ray Buildup Factors of Concretes Containing Limonite Ore
(Elsevier Science Sa, 2015) Oto, Berna; Yildiz, Nergiz; Korkut, Turgay; Kavaz, Esra
Neutron dose transmissions for fast neutrons produced by 5.486 MeV alpha particles on beryllium are measured in concrete samples with and without limonite ore to investigate their neutron shielding qualities. Using measured values, macroscopic removal cross-sections (Sigma(R), cm(-1)) have been determined experimentally and also Sigma(R)values have been calculated theoretically using the elemental composition of the concrete mixes. The best neutron shielding property of concrete sample containing 100% limonite ore (FCL: fine and coarse limonite) was found. Additionally, energy absorption buildup factor (EABF) and exposure buildup factor (EBF) of concrete sample were calculated using the five-parameter Geometric Progression (G-P) approximation in the energy range of 0.015-15 MeV for penetration depths up to 40 mean free path (mfp). The incident photon energy and penetration depth dependence of buildup factors were examined. Finally, we observed that concrete samples have maximum values of buildup factors in the intermediate energy region around 0.1-0.3 MeV. FCL has the minimum values of both of the buildup factors. FCL has the excellent gamma shielding properties compared to the concrete samples. (C) 2015 Elsevier B.V. All rights reserved.
Nuclear Radiation Shielding and Mechanical Properties of Colemanite Mineral Doped Concretes
(Taylor & Francis Ltd, 2019) Oto, Berna; Madak, Zekiye; Kavaz, Esra; Yaltay, Namik
The present research focused on the investigation of photon and fast neutron shielding parameters of colemanite mineral doped and undoped concretes. The fabricated concretes have been exposed to gamma rays at 59.5 and 81 keV energies and the measurements have been carried out with NaI(Tl) detector. The parameters of effective atomic number (Z(eff)) and electron density (N-el) have been determined experimentally and theoretically. The exposure buildup factor (EBF) and energy absorption buildup factor (EBF) have been computed utilizing the Geometric progression (G-P) fitting method. In addition to the photon shielding parameters, the macroscopic effective removal cross-section calculations for fast neutron (sigma(R)) were performed. As a result, it was observed that the concretes doped with colemanite mineral are not very effective in gamma radiation shielding. On the contrary, it was observed that concretes with colemanite were more effective in shielding fast neutrons and the fast neutron removal cross-section values increased with increasing colemanite concentration in the concrete. Additionally, compressive strength values (MPa) of concretes were tested using ALFA TESTING (B001-PC) 200 tons capacity device.