Neutron Total Cross Sections Research Articles

The new Device for Indirect Capture Experiments on Radionuclides at LANSCE: Efforts on measuring the resonance(s) responsible for the extremely large 88Zr (n,γ) cross section

The thermal neutron capture cross section of 88Zr was recently reported to be the second largest in nature with the largest resonance integral measured. Presumably, these very large values are caused by a resonance or resonances very near thermal energy. Determining their energies and widths, and hence the shape of the cross section away from thermal energies,is useful for applications. The short half-life (83.4 days) and associated large background, renders direct measurements of the neutron capture cross section impossible using current techniques. However, it is possible to measure the total neutron cross section, and hence the resonance properties, using the newly commissioned Device for Indirect Capture Experiments on Radionuclides (DICER) at the Los Alamos Neutron Science Center (LANSCE). Transmission measurements are utilized as a surrogate method to perform capture measurements. The 88Zr needed for a DICER measurement was produced at the Isotope Production Facility (IPF) and cleanly separated from the production target material. A description of the new instrument, efforts and preliminary results on 88Zr will be presented.

Templates of expected measurement uncertainties for total neutron cross-section observables

This paper provides a template of expected uncertainties and correlations for measurements of total neutron cross-section observables by transmission. Measurements with time-of-flight and mono-energetic neutron sources are covered. The information required for evaluations in the resonance region and high energy region is detailed, along with the template of uncertainties and correlations that can be used in the absence of other information.

Total thermal neutron cross section measurements of hydrogen dense polymers from 0.0005–20 eV

Hydrogen dense polymers, specifically polyethylene, polystyrene, and Plexiglas, have served as neutron moderator and reflector materials in hundreds of separate critical benchmark experiments because of their low cost and abundance of hydrogen. In order to accurately model and simulate these critical benchmarks, the thermal scattering law (TSL) evaluation that governs how neutrons will thermalize must be well understood and rigorously validated. To support this validation, researchers at Rensselaer Polytechnic Institute performed total neutron cross section measurements for high-density polyethylene & polystyrene over the energy range 0.0005–20 eV and for Plexiglas G & Plexiglas G-UVT over the energy range 0.0005–3 eV. Comparisons were made between the measured cross section and that predicted by the ENDF/B-VIII.0 and Oak Ridge National Laboratory/European Spallation Source/Rensselaer Polytechnic Institute TSL evaluations for polyethylene, Plexiglas, and polystyrene, as available. These experiments represent the first total neutron cross section measurements for polystyrene.

New Material Exploration to Enhance Neutron Intensity below Cold Neutrons: Nanosized Graphene Flower Aggregation.

It is proposed that nanosized graphene aggregation could facilitate coherent neutron scattering under particle size conditions similar to nanodiamonds to enhance neutron intensity below cold neutrons. Using the RIKEN accelerator-driven compact neutron source and iMATERIA at J-PARC, we performed neutron measurement experiments, total neutron cross-section and small-angle neutron scattering on nanosized graphene aggregation. For the first time, the measured data revealed that nanosized graphene aggregation increased the total neutron cross-sections and small-angle scattering in the cold neutron energy region. This is most likely due to coherent scattering, resulting in higher neutron intensities, similar to nanodiamonds.

Recycling of optical borosilicate waste glasses by Y2O3 doping for radiation shielding applications

In the present study, borosilicate glass-ceramics doped with Y2O3 were prepared and characterised for their structure and shielding prowess. Borosilicate waste glasses doped with Yttrium as a rare earth element from Y2O3 were prepared through the cold isostatic press method. The glass-ceramics had the chemical formula 81SiO2-12B2O3–4Na2O-3Al2O3-XY2O3, where X = 0, 10, 20% by weight. The structure of the prepared glasses was studied by the X-ray diffraction method while the density and hardness of the sample were measured experimentally. The ability of the glasses to absorb gamma-ray photons, moderate fast neutrons, and thermal neutrons was estimated from Monte Carlo simulations and established theoretical calculations. Samples containing 0% and 10% weight fraction exhibited mainly glassy structures, while the XRD spectrum of the sample containing 20% Y2O3 by weight displayed a glass-ceramics structure. The Vickers hardness values were calculated as 453, 501 and 551 HV under a 0.5 kg load for Y2O3 content of 0, 10, and 20 wt%. The density of the pristine borosilicate glass was 2.03 gcm−3. The addition of 10% and 20% by weight of Y2O3 increased the density by 9.85% and 18.07%, respectively. The mass attenuation coefficient values show strong energy fluctuations from 0.02046 to 5.18560 cm2/g for BS1, 0.02179–6.49902 cm2/g for BSY1, and 0.02313–7.81340 cm2/g as E decreases from 15 MeV to 15 keV. In addition, increasing the Y2O3 weight proportion in the samples increases photon buildup. The introduction of Y2O3 into the pristine borosilicate glass was found to increase the removal and total cross-sections for fast and moderated neutrons, respectively. The glass-ceramics demonstrated attributes useful for radiation absorption applications.

Neutron total and capture cross-section measurements of 155Gd and 157Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI

ABSTRACT Neutron total and capture cross–section measurements of 155Gd and 157Gd were performed with Li-glass detectors and a NaI(Tl) spectrometer in the ANNRI at the MLF of the J-PARC. The neutron total cross sections were determined in the energy region from 5 to 100 meV, and those at the thermal neutron energy were obtained to be 59.4 1.7 and 251.9 4.6 kilobarn for 155Gd and 157Gd, respectively. The neutron capture cross sections were determined in the energy region from 3.5 to 100 meV with an innovative method, and those at the thermal energy were obtained as 59.0 2.5 and 247.4 3.9 kilobarn for 155Gd and 157Gd, respectively. The present total and capture cross sections agree well within the standard deviations. The results for 155Gd were found to be consistent with the values in JENDL-4.0 and the experimental data given by Møller et al., Mastromarco et al. and Leinweber et al. Those for 157Gd agreed with the evaluated data in JENDL-4.0 and the experimental data by Møller et al. and Mastromarco et al. However, they disagree (11% larger) with the experimental result by Leinweber et al.

Comparative shielding features for X/Gamma-rays, fast and thermal neutrons of some gadolinium silicoborate glasses

X/Gamma-rays, fast and thermal neutrons shielding properties for eight gadolinium based glasses (labeled as S1:S8) have been investigated at energies between (0.015–15 MeV) using MCNPX code and WinXcom software. The correlation coefficient (R2) was used to assess the degree to which MCNPX results are related to that of WinXcom. For all glass samples, R2 was found close to 1, this infers a perfect degree of correlation between the MCNPX and WinXcom results. Multiple parameters including, mass attenuation coefficient (μ/ρ), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), electron density (Nel), radiation protection efficiency (RPE), exposure and energy absorption buildup factors (EBF & EABF), specific absorbed fraction of energy (SAFE), kerma relative to air (Ka), macroscopic effective removal cross section (ΣR), and total neutron cross-section of thermal neutron (σt) were determined and compared with that of other frequently used along with recently studied shielding materials. The results show that, as the Gd2O3 content increases, the μ/ρ, Zeff, Nel, RPE, ΣR and σt values increase while HVL, MFP, EBF, EABF, and SAFE values all decrease as follow: the values of MAC ranges from 0.0173 to 1.906 and 0.0281–31.831 cm2 g−1; Zeff varied from 6.027 to 8.836 and 10.497–45.659; HVL varied from 0.152 to 16.750 and 0.005–5.533 cm; Nel varied (from 2.8 to 4.25) x1023 and (2.88–13.96) x1023 (electrons/g) for S1 and S8 respectively. In addition, among all studied glasses, S8 glass sample (with G2dO3 content of 35% mol) provided a fully protection for X-rays (RPE = 100%). Moreover, when compared to other common shielding materials and recently studied glasses (in terms of MFP), the S8 sample was found to have the highest attenuation performance relative to many of these materials. In terms of fast and thermal neutrons, the addition of Gd2O3 had a great effect on increasing the attenuation capability for fast and thermal neutrons as follow: the ΣR and σtotal values were increased from 0.120 to 0.145 cm−1 and from 123.99 to 15,258.73 b for S1 and S8 respectively. In addition, the S8 sample was found to have the highest neutron attenuation performance when compared to other common shielding materials and recently studied glasses. Therefore, S8 sample found to have superior characteristics for radiation and neutron shielding applications. The findings of this study might be highly useful in the future for medicinal and industrial applications.

Total thermal neutron cross section measurements of yttrium hydride from 0.0005 - 3 eV

Yttrium hydride serves as a neutron moderator material that enables compact, high temperature nuclear reactors. However, in order to accurately design and simulate a nuclear system relying upon yttrium hydride, the fundamental nuclear data of yttrium hydride must be well understood. Thermal neutron scattering law (TSL) evaluations represent an important aspect of nuclear data as thermal scattering can drastically alter the neutron multiplication factor of a system. Therefore, to support evaluation and validation of thermal neutron scattering for yttrium hydride, researchers at Rensselaer Polytechnic Institute (RPI) performed total thermal neutron cross section measurements for YH1.68 and YH1.85 over the energy range of 0.0005 - 3 eV. These measurements represent the first total cross section measurements for yttrium hydride that encompass the entire thermal region. Comparisons were made against the ENDF-B/VIII.0, Zerkle & Holmes and Oak Ridge National Laboratory TSL evaluations, where generally good agreement was found.

Study of the 176Hf(n,2n)175Hf cross section at 18.9 MeV

Neutron nuclear reactions can provide significant information in the field of nuclear physics and applications. Hafnium (Hf) is one of the rare-earth isotopes with a relative large neutron total cross-section in the thermal neutron energy region and neutron induced reactions in reactor materials could lead to the production of long-lived isomeric states of Hf isotopes. Thus, the knowledge of neutron cross-sections on Hf isotopes is of great importance for basic research in Nuclear Physics as well as for applications concerning the interaction of neutrons with matter. In this study measurements of experimental cross section for the 176Hf(n,2n)175Hf and 180Hf(n,n΄γ)180mHf reactions were carried out, using the activation technique. The neutron beam energy at 18.9 MeV was produced via the 3H(d,n)4He reaction at the 5.5 MeV Tandem Van de Graaf accelerator laboratory of NCSR “Demokritos”. A thin metallic foil of natural Hf was used, while for the determination of the neutron flux at the target position a reference foil of Al was placed at the back of the Hf target. The irradiation was continuous for 28 hours leading to a total neutron fluence of 1010 n/cm2 and a BF3 detector was used for monitoring the neutron flux during the irradiation. After the end of irradiation, the activity of the Hf target and the Al foil were measured off-line by two HPGe detectors. Both detector efficiencies were obtained using a calibrated 152Eu source, placed in the same distance as the target and the reference foil. The 176Hf(n,2n)175Hf reaction has been corrected from the contribution of 177Hf(n,3n)175Hf and the 174Hf(n,γ)175Hf reactions and the 180Hf(n,n΄γ)180mHf reaction from the 179Hf(n,γ)180mHf. Theoretical calculations of the 174Hf(n,2n)175Hf, 176Hf(n,2n)175Hf and 180Hf(n,n΄γ)180mHf reaction cross-sections have also been performed using the nuclear statistical code “EMPIRE 3.2.3” and they have been compared with the data.

Investigations on Lanthanide polymers for radiation shielding purpose

The current study involves the X-ray/gamma and neutron/EMI shielding and change in mechanical properties of selected lanthanide polymers such as Lanthanum polymer, Cerium polymer, Praseodymium polymer, Gadolinium texaphyrin polymer, Terbium co-ordination polymer and Erbium phosphate hydrate polymer. The X-ray/gamma, neutron and EMI shielding parameters are studied in detail for all the selected polymers. Among all the selected polymers, Erbium phosphate hydrate polymer shows larger values of mass attenuation coefficient, absorption buildup factor, Zeff, Ne, specific absorbed fractions of energy, radiation protection efficiency, kinetic energy released in matter, relative dose, neutron total interaction cross section and absorption cross section values. Furthermore, the EMI shielding parameter (total shielding effectiveness) was also found to be larger for Erbium phosphate hydrate polymer in near infrared, mid infrared, far infrared, ultra high frequency (UHF), very high frequency, high frequency radio waves, middle frequency radio waves, low frequency radio waves and very low frequency radio waves. This clearly indicates that Erbium phosphate hydrate polymer might be used as a good shielding material for X-ray/gamma, neutrons and EMI radiations. We have also reported the change in mechanical properties of the studied lanthanide polymers due to the interaction with X-rays/gamma rays. The mechanical properties remains unchanged in the region where pair production and photoelectric effect dominates. Change in the mechanical properties is observed in the region where Compton scattering dominates, indicating that the change in mechanical properties due to interaction of radiation is also an important parameter while selecting the shielding materials. Present study may be useful in the selection of new shielding material.

Analytical investigation on the shape of the response functions of Superheated Drop Detectors using Evaluated Nuclear Data

In this paper, the response matrix of Superheated Drop Detector was analyzed and investigated using Evaluated Nuclear Data. Elastic, nonelastic and total neutron cross sections were extracted and used for calculating the probability of the production of charged particles as a result of neutron interaction with superheated liquid nuclei. The values of the response functions in each energy are proportional to the probability of the production of charged particles. It was proposed that the response function can be represented as the multiplication of the total neutron cross sections by a monotonic probability function. The parameters associated with this function change with changing the physical properties of the detector such as temperature or external pressure. The growth rate of this function decreases when the temperature decreases or the external pressure on detectors increases due to increase in threshold energy for the generated charged particles. So the growth rate and shape of this function are set by parameters which are dependent on the physical properties of Superheated Drop Detectors.

A synergistic effect of heavy metal oxides to enhance the physical, optical, and radiation-absorption properties of TeO2-Li2O-BaO glasses

A series of 75TeO2-(20-x)Li2O-xBaO glasses was successfully synthesized using the melt-quenching method. The glass samples were labeled as TLB05, TLB10, TLB15, TLB20 and TLB25 for x = 5, 10, 15, 20 and 25 mol% respectively. The prepared glasses were studied for their structural, optical, and radiation shielding properties. The optical band gap of the glasses decreased linearly from 3.45 to 3.28 eV with BaO in the range 5−25 mol%. The analysis of the thermal properties shows an increase in Tg values with the replacement of Li2O by BaO. The gamma ray shielding coefficients for the glasses estimated by FLUKA simulation and validated by XCOM varied from 0.0329 to 1.4383 cm2g−1, 0.0332 – 1.4879 cm2g−1, 0.0334 – 1.5327 cm2g−1, 0.0335 – 1.5671 cm2g−1, and 0.0336 – 1.5964 cm2g−1 for BaO concentration of 5%, 10%, 15%, 20%, and 25% respectively. Generally, the introduction of BaO improved the photon and charged particles (electron, proton, alpha particle, carbon ions) absorbing parameters of the glasses. The fast neutron removal cross section of the TLB glasses grew from 0.0995 to 0.1014 cm−1 as the molar concentration of BaO declines from 25 to 5 mol%. The increase in the BaO content also quenched the thermal neutron absorption cross section. For TLB5 – TLB25, the coherent, incoherent, absorption, and total thermal neutron cross sections varied between 1.0582 and 1.2059 cm−1, 0.1251 – 0.0024 cm−1, 9.5411 – 0.0876 cm−1, and 10.7244 – 1.2958 cm−1 accordingly. In general, TLB25 displayed the most effective photon shielding ability but the weakest neutron absorber. The TLB glasses in addition showed superior radiation shielding ability compared to some conventional shields.

Effect of Nb2O5 inclusion on the radiation shielding efficiency of TeO2–ZnO–LiF–NaF glass system

The objective of this study is to investigate the effect of Nb2O5 inclusion on the optical, photon absorption, fast neutron moderation, and thermal neutron absorption features of 75TeO2 – 10ZnO – 5LiF – (10-x)Nb2O5 – xNaF (where x = 10, 6, and 2 mol %) glasses that are denoted by TLFZNN1, TLFZNN2, and TLFZNN3, respectively, as x increases. The linear attenuation coefficients (LAC) and associated parameters were estimated by the use of FLUKA simulations and XCOM computations. Analysis of the estimated shielding parameters shows that, at equal photon energy, LAC increases as Nb2O5 content of the glasses increases relative to NAF. The LAC changed in the range of 0.7892 – 0.1836, 0.8238 – 0.1941, and 0.846 – 0.2015 for 0.284 <‾E <‾ 2.506 MeV. The half value layer (HVL) is observed in the order of TLFZNN1 > TLFZNN2 > TLFZNN3. This trend indicated that there is an increase in the radiation protection efficiency of the glasses as the density (ρg) and Nb2O5 content increases. Zeff varies between 21.27 and 27.85, 21.18 – 27.59, and 21.20 – 27.42 for TLFZNN1, TLFZNN2, and TLFZNN3 correspondingly. Fast neutron removal cross section ΣR and total thermal neutron cross section σt are also estimated for the glasses. ΣR grew from 0.0967 to 0.1057 cm-1 while σt decays with Nb2O5 content increased in the glasses. Compared to standard shielding glasses and concrete, the TLFZNN glasses show outstanding shielding abilities.

Nuclear shielding characteristics of Sm3+ doped borosilicate glasses containing Na2O, PbO and ZnO

The aim of this paper is to investigate the photon, charged particles, fast and thermal neutrons absorption characteristics and dose rates of Sm3+ doped borosilicate glasses containing Na2O–PbO–ZnO via theoretical method and simulation code. The linear attenuation coefficients of SBNPZS4 glasses are the highest whereas the mass attenuation coefficients of SBNPZS1 glasses are the highest in the present SBNPZS glasses. The SBNPZS4 has the lowest half value layer and mean free path values among the SBNPZS glasses and compared standard shielding materials therefore SBNPZS4 has the better photon absorption characteristics. The effective atomic number, effective electron density, mass energy-absorption coefficient, specific gamma ray constant, and gamma dose rate values change as SBNPZS4<SBNPZS3<SBNPZS2<SBNPZS1. The ranges of SBNPZS glasses for charged particles modify as SBNPZS4<SBNPZS3<SBNPZS2<SBNPZS1. Both fast neutron removal cross section and total cross section for thermal neutron vary in order of SBNPZS1<SBNPZS2<SBNPZS3<SBNPZS4 hence SBNPZS4 owns the highest fast and thermal neutron absorption characteristics. Consequently, SBNPZS glasses can be suggested and developed as photons, neutrons and charged particles shielding materials.

Estimation of radiation protection ability of borate glass system doped with CdO, PbO, and TeO2

This report presents the gamma-rays and neutron interacting parameters of the newly developed xCdO – 20PbO–10TeO2 – (69-x) B2O3–1CuO glass system with the view to applying them for nuclear protection uses. The glasses were coded as CdPTBCu1 – 4 representing molar concentration of CdO form 0–15%. The mass attenuation coefficient (MAC) of the glasses at gamma radiation energies 662–2506 keV were estimated using FLUKA. Monte Carlo simulation and NIST library. The simulation results compared well with that of NIST library within 2% margin. The MAC declines with energy but generally increases as CdO concentration increases in the glasses. At 0.284 MeV, the MAC values of CdPTBCu1, CdPTBCu2, CdPTBCu3, and CdPTBCu4 were equal to 2.459×10−1, 2.458×10−1, 2.457×10−1, and 2.447×10−1 cm2/g, respectively. While at 2.51 MeV, the values were 4.023×10−2, 4.023×10−2, 3.982×10−2, and 3.994×10−2 cm2/g, respectively. Other photon shielding factors like the effective atomic layer, transmission factor, self-absorption correction factor, and mean free path show that the increase in CdO content improves the photon shielding abilities of CdPTBCu specimens. Furthermore, the fast neutron removal cross section (ΣR) and their total thermal neutron cross section (σT) of the glasses were estimated. ΣR increased from 0.10211 to 0.10775 cm−1 while σT grew from 111.21 to 442.73 b. The increase in CdO content had a positive impact on the photon, fast, and thermal neutron shielding ability of the CdPTBCu glasses. Comparatively, the photon and neutron shielding ability of the present glass system is superior to some conventional and recently studied glass shields. The CdPTBCu glasses are thus potentially useful as photon and neutron absorbers for nuclear radiation protection applications.

A new method of gas reservoir evaluation based on neutron cross section logging

It is a widely used method to evaluate gas reservoirs by measuring inelastic gamma rays. A petrophysical parameter fast neutron cross section (FNXS) was proposed to describe the inelastic gamma for gas reservoir evaluation. FNXS is the 14 MeV neutron macroscopic elastic scattering cross section. However, the description of inelastic gamma using FNXS is only a first order approximation. Therefore, in some scenarios, the evaluation of gas saturation is not accurate enough. In this paper, we propose a new parameter total fast neutron cross section (TFNXS) based on the inelastic gamma generation and attenuation theory. TFNXS is the sum of macroscopic elastic and inelastic scattering cross sections of 14 MeV neutrons. The physical meaning of TFNXS is the probability of inelastic and elastic scattering between neutrons and formation. TFNXS is a new formation property independent of neutron macroscopic capture cross section (Sigma). TFNXS value of gas is quite different from that of matrix minerals, water, oil and clay, so TFNXS is more sensitive to gas-bearing formation and can identify gas reservoir more effectively. We compared the sensitivity of TFNXS and FNXS to gas. The sensitivity of TFNXS to gas is similar to that of FNXS. The effects of different formation conditions on the measurement accuracy of the TFNXS and the FNXS are analyzed with the Monte Carlo method. Compared with FNXS, TFNXS can be obtained more accurately in water and oil layers. Different clay minerals have different effects on TFNXS and FNXS. TFNXS is less affected by wellbore environment, such as well diameter and wellbore fluid, than that of FNXS. We evaluate the application results of TFNXS and FNXS in various model wells. Both TFNXS and FNXS can effectively identify gas-bearing formations. The accuracy of using TFNXS to obtain gas saturation is higher than that of FNXS. TFNXS can more accurately monitor reservoirs and evaluate low porosity gas reservoirs than FNXS.

Measurement of total neutron cross section of natural lithium at China Spallation Neutron Source Back-n facility

Lithium is one of the main materials of fuel carrier salt in molten salt reactors. Its neutron cross section provides an important basic datum for physical design of molten salt reactor core and for evaluating the safety of the core during operation. The total neutron cross sections of natural lithium samples with thickness values of 8.00 mm and 15.0 mm are measured, respectively, in an energy range from 0.4 eV to 20 MeV by using a neutron total cross section spectrometer (NTOX) with the transmission method at the Back-n white neutron source of China Spallation Neutron Source (CSNS Back-n) with a 76.0 m time-of-flight path. High quality experimental data are obtained, especially in the energy region of keV and below, which supply a significative supplement of the data, thereby providing more abundant and reliable experimental data for nuclear data evaluation of lithium. Additionally, a theoretical analysis is carried out under the guidance of 1/&lt;i&gt;v&lt;/i&gt; law and the multilevel R-matrix theory. And the resonance parameters of n+&lt;sup&gt;6,7&lt;/sup&gt;Li reaction around the energy of 260 keV are extracted from the measured data.

Synthesis, physical, optical, structural and radiation shielding characterization of borate glasses: A focus on the role of SrO/Al2O3 substitution

In a bid to expand the amount of information available on glass systems and their potential applications for radiation shielding design, glass samples with the compositions (30-x)SrO-xAl 2 O 3 –68B 2 O 3 –2V 2 O 5 (x = 5, 7.5, 10, 12.5&15 mol %) coded as SABV0 - 4 were prepared by the melt-quenching technique and analyzed for their optical, structural, physical, and radiation shielding features. The glassy (amorphous) nature of the SABV glass samples was affirmed by broad peaks of X-ray diffraction spectra. Calculated values of density and molar volume shown opposite behavior and the variation of these values were discussed as structural modifications in the glass matrix. From recorded optical absorption spectra optical band gap energy (Eg)-indirect transition, Urbach energy and optical basicity were estimated. FTIR spectra were recorded for all the samples in the range 400 cm −1 to 4000 cm −1 . The FTIR absorbance spectra unveiled the SABV network structure mainly incorporating of BO 3 and BO 4 units. Raman spectroscopy is achieved to detect the structural changes and at higher wavenumber, B–O stretching modes in [BO 3 ] observed with one or two NBO's. The results of ESR spectra of glasses have indicated the highly covalent environment of vanadium ions. Analysis of the photon shielding parameters of the glasses which were obtained primarily from FLUKA Monte Carlo simulations and XCOM computations revealed photon energy and glass chemical composition dependence. The mass attenuation coefficient and effective atomic number ranged from 0.2668 to 0.3385 cm 2 g -1 and 12.98–15.93 accordingly as the weight fraction of Sr increased from 16.06 to 26.72% in the glasses. Generally, photon shielding ability of the SABV glasses follows the trend: SABV0 > SABV1 > SABV2 > SABV3 > SABV4. The thermal neutron total cross section follows the same trend with values fluctuating between 71.9553 and 80.6268 cm −1 . However, SABV1 showed superior fast neutron moderating capacity among the glasses. The present SABV glasses showed outstanding photon shielding ability compared to common shields. The prepared glasses are thus suitable candidates for radiation protection applications.

Measurement of Neutron Total Cross Section of Th in 0.008-0.1 eV at TMSR-PNS

Measurement of Neutron Total Cross Section of Th in 0.008-0.1 eV at TMSR-PNS

Monte Carlo Simülasyonu Kullanılarak B4C, B2O3, Sm2O3 ve Gd2O3 Katkılı Polimer Matrisli Kompozitlerin Termal ve Hızlı Nötron Zırhlama Özelliklerinin İncelenmesi

In this study, thermal (2.53*10-8 MeV) and fast (2 MeV) neutron total macroscopic cross-sections of paraffin, polycarbonate, and polyester matrix polymers doped with B4C, B2O3, Sm2O3, and Gd2O3 (at weight percentages of 5%, 10%, 15%, 20%, and 25%) were computed by using Monte Carlo simulations. Additionally, the macroscopic effective removal cross-section ) of fast neutrons was theoretically computed based on the mass removal cross-section values ) for various elements in polymers and additives. The obtained results show that the highest thermal neutron total macroscopic cross-section was obtained in polycarbonate doped with Gd2O3, and the highest fast neutron total macroscopic cross-section was observed in paraffin doped with Sm2O3. Besides, the paraffin provided the highest fast neutron total macroscopic cross-section for all additives. The results of this study provide a good understanding of shielding properties of paraffin, polycarbonate, and polyester matrix polymers doped with B4C, B2O3, Sm2O3, and Gd2O3 against thermal and fast neutrons.