Radiation Barrier Research Articles

Impact of adding bismuth oxide nanoparticles functionalized with graphene oxide nanosheet on the polyvinyl chloride shielding properties

This study investigates the enhancement of polyvinyl chloride (PVC) by incorporating Bi2O3-GO nanocomposites. We produced nanocomposites with varying concentrations (1, 2.5, 5, and 10 wt%). The prepared samples were characterized using scanning electron microscopy (SEM) and Fourier transform infrared spectroscopy (FTIR). X-ray diffraction (XRD) and thermogravimetric analysis (TGA) were also used. As well as the shielding effectiveness against ultraviolet rays and gamma radiation from 137Cs and ⁶⁰Co sources at energies of 662, 1173, and 1275 keV. Results indicate that the addition of Bi2O3-GO significantly improves the thermal stability of PVC, as evidenced by higher decomposition temperatures from TGA. The absorption coefficient increases, while energy gap values decrease with increased nanofiller weight concentrations. The linear attenuation coefficient (LAC) also rises with increasing nanofiller content and decreases with higher gamma-ray energies. Results were consistent with Phy-X software simulations. The sample with 10% wt of Bi2O3-GO composite demonstrated a highly fast neutron removal cross section (FNRC) and reduced mean free path (MFP). This indicates strong potential for use as a safe, environmentally friendly alternative to lead-based shielding materials. These PVC/Bi2O3-GO nanocomposites could be effectively utilized in radiation barriers and protective screens in settings involving neutron and low-energy gamma radiation, such as in radiography and radioactive material management.

Modified F(R,T2)-Gravity Coupled with Perfect Fluid Admitting Hyperbolic Ricci Soliton Type Symmetry

In the present research note, we discuss the energy–momentum squared gravity model F(R,T2) coupled with perfect fluid. We obtain the equation of state for the perfect fluid in the F(R,T2)-gravity model. Furthermore, we deal with the energy–momentum squared gravity model F(R,T2) coupled with perfect fluid, which admits the hyperbolic Ricci solitons with a conformal vector field. We provide a clue in this series to determine the density and pressure in the radiation and phantom barrier periods, respectively. Also, we investigate the rate of change in hyperbolic Ricci solitons within the same vector field. In addition, we determine the different energy conditions, black holes and singularity conditions for perfect fluid attached to F(R,T2)-gravity in terms of hyperbolic Ricci solitons. Lastly, we deduce the Schrödinger equation for the potential Un with hyperbolic Ricci solitons in the F(R,T2)-gravity model coupled with perfect fluid and a phantom barrier.

Identification of Urban Heat Island Potency in Janten Village area due to Aerotropolis Development

Abstract Special Region Yogyakarta Province experiences an increase in heat every year based on land surface temperature data in each region. This increase in heat is caused by the decreasing function of green land in rural areas over time, so that the land surface experiences increased exposure to sunlight due to reduced radiation barriers and heat absorption, and has the potential to give rise to an Urban Heat Island. The decline in rural areas as green areas is due to industrial development, one of which is the planning of the Aerotropolis area in Janten Village, Wates Regency, Kulon Progo, Yogyakarta. Aerotropolis is a regional development concept that makes airports the center of the economy, mobilization, transportation, and industry. This paper aims to analyze the magnitude of the potential arising from Land Use-Land Change (LULC) due to the Aerotropolis planning concept in Janten Village. The main data collection was carried out through direct measurements in the field using a Micro Weather Station (MWS) as a recorder of climate conditions and a thermal flir camera to capture surface temperatures. The data taken will be processed using experimental methods using the ENVI-Met application according to modeling of the existing conditions and microclimate of Janten Village.

The Electromagnetic Shielding Properties of Biodegradable Carbon Nanotube–Polymer Composites

In this article, the electromagnetic shielding properties of carbon nanotube–polymer nanocomposites are presented. The composite fabrication technique is spray-drying, the usage of which leads to a uniform dispersion of carbon nanotubes (CNTs) in a polymer matrix. Obtaining good filler dispersion is necessary to form a continuous, electrically conductive network of CNTs inside the polymer matrix. In the described nanocomposites, the network of conductive filler particles acts as an electromagnetic radiation barrier. For this reason, developing a highly effective fabrication method is very important. Also, the method should be simple enough to be easily adopted in an industrial environment. The authors shows in this text that both goals mentioned are achieved. The obtained nanocomposite material not only has electrostatic shielding capabilities but comprises electromagnetic shielding properties, which fulfills the main goal of the presented work. It is also worth mentioning that the developed manufacturing method allows for the usage of different fillers and polymers and thus the fabrication of materials capable of meeting a wide range of requirements.

Low-concentration imiquimod treatment promotes enhanced skin barrier functions through epidermal melanization reaction regulation.

The primary function of the skin is to form a mechanical, permeability, antimicrobial, and ultraviolet radiation barrier, which is essential for maintaining physiological homeostasis. Our previous studies demonstrated that cutaneous pigmentation could promote skin barrier function in addition to providing anti-ultraviolet irradiation defense. The present study aimed to develop a new regimen that enhances skin barrier function by regulating skin pigmentation using low-concentration imiquimod. Results showed that topical application of low-concentration imiquimod effectively induced skin hyperpigmentation in the dorsal skin and external ear of mice without inducing inflammatory cell infiltration. An in vitro study also revealed that low-concentration imiquimod did not induce any cytotoxic effects on melanoma cells but triggered excessive melanin synthesis. In coculture systems, low-concentration imiquimod was noted to increase tyrosinase activity in a broader cellular context, revealing the potential role of neighboring cells in melanin production. The next-generation sequencing result indicated that PKCη and Dnm3 might regulate melanin synthesis and release during imiquimod treatment. Overall, our study presents new insights into the regulation of melanin production by low-concentration imiquimod, both in a mice model and cultured cells. Furthermore, our study highlights the potential benefits of imiquimod in promoting melanin synthesis without causing skin disruptions or inducing inflammation, validating its potential to serve as a method for enhancing skin barrier functions by regulating the epidermal melanization reaction.

Studies on structural, optical, thermal and low energy shielding for gamma rays for the ZSBP glasses

By employing the melt-quenching technique, the ZnO–SrO–B2O3–PbO (ZSBP) glasses have been successfully fabricated. The derivative of Absorption Spectra Fitting (DASF) method was used to study the energy band gap (Eg) of the glasses which decreases from 3.57 eV to 3.39 eV. The structural properties have been studied using the Raman spectroscopy. The glass transition temperature (Tg) decreases with increase in concentration of the lead oxide. The current study examines the radiation shielding properties at 30.80–444 keV. The addition of PbO to the glasses resulted in a proportionate increase in the mass attenuation coefficient (MAC), suggesting a diminishing tendency in radiation transmission. At 30.80 keV, the MAC values are extremely high and range from 18.06 to 21.11 cm2/g. As density rises, the half value layer (HVL) decreases. In addition, the average HVL (HVL‾) decreases. The glass thickness required to reduce the radiation intensity to 90 %, 50 %, 25 %, and 10 % of its initial value is investigated at an energy of 35.80 keV. The T90 %, T50 %, T25 %, and T10 % values are 0.0020, 0.0132, 0.0264, and 0.0439 cm, respectively. The results suggest that a greater thickness of the radiation barrier is necessary to attain the necessary degree of attenuation.

Influence of Epilobium parviflorum Herbal Extract on Physicochemical Properties of Thermoplastic Starch Films.

In this study, for the first time, Epilobium parviflorum Schreb. (E, hoary willowherb) aqueous extract was introduced into edible biopolymer films and its influence on physicochemical properties of the final products were investigated. Potato starch was gelatinized in the herbal tea to obtain thermoplastic starch (TPS) films via the casting method. The characterization of the films included mechanical, antioxidative, water (WVTR, contact angle, swelling degree) and UV radiation barrier properties as well as microstructure analysis (SEM). Obtained results indicated that the presence of the extract (rich in phenolic compounds) in the films acted as a co-plasticizer for starch and led to a higher elongation at break, up to 70%, with a parallel increase in tensile strength up to ca. 9 MPa. Moreover, TPS films with E exhibited lower WVTR values and absorption of UV light in comparison with the control TPS film. DPPH scavenging activity of TPS E films immersed in methanol was ca. 92%, and it was related to the release of the extract into liquid media. Novel TPS E films are characterized by multifunctional properties that can be used, e.g., in the active packaging sector.

Evaluating energy generation of a building-integrated organic photovoltaic vertical façade: A case study of Latin America's pioneering installation

Building-integrated photovoltaics play a key role in the reduction of greenhouse gases emission towards sustainability in the building and construction sector. Organic solar technology holds several advantages such as lightweight, flexibility and semitransparency, suiting well for this type of application. When integrated into windows and facades, it provides a dual benefit: it acts as a solar radiation barrier, improving indoor thermal comfort, while also generating off-grid power. Besides that, organic devices are known to be more efficient than traditional photovoltaics based in silicon in diffuse and low light conditions. Nevertheless, only a few studies have been conducted in the area employing large-area commercial modules, in real operational conditions and for a long-term period. This work has the purpose of reducing this gap and shine a light on this debate bringing an analysis based on real data of a set of organic panels laminated in glass in a vertical pioneer installation in Latin America. For this, several linear regression models were tested to predict the energy generation from meteorological data and solar position throughout four years of operation, and the best models developed achieved 0.76 and 0.81 values for R2 with validation data, respectively for simple and multiple regressions. A visual analysis showed that the OPV system produced more energy in winter due to lower solar altitude, despite lower global radiation levels. The most significant variables in the models were the global solar radiation and the solar altitude. The use of glass lamination and vertical orientation likely preserved the performance of the panels, keeping energy generation consistent over four years, akin to the first year.

ANALISIS PAPARAN RADIASI SKYSHINE DINDING RUANGAN ANGIOGRAFI/CATHLAB RUMAH SAKIT MITRA KELUARGA KEMAYORAN BERSUDUT GANTRY 0 DERAJAT

Based on NCRP (2005), skyshine radiation generally occurs in radiotherapy facilities, the cause of which is that some radiation facilities are designed with minimal shielding on the linear accelerator (Linac) ceiling. As time goes by, Skyshine radiation monitoring is not only focused on radiotherapy facilities, but radiodiagnostic facilities also need to be monitored, especially interventional radiology, which uses real-time X-ray radiation at certain times. Regarding this matter, it is necessary to check whether the walls of the existing angiography room or cath lab are protected from skyshine radiation. This study aims to determine whether the Angiography/Cathlab room at Mitra Keluarga Kemayoran Hospital does not produce skyshine radiation. The method for measuring skyshine radiation exposure uses a survey meter at a distance of 30 cm and 2 meters 3 times from the outer wall of the Angiography/Cathlab room on the north, south, and west sides of the gantry; then the gantry is positioned at 0 degree. The research results show that radiation exposure is 0.14 µSv/hour at a distance of 30 cm. Skyshine radiation was detected at a distance of 2 meters with an exposure value of 0.32 µSv/hour on the west side of the gantry and 0.39 µSv/hour on the north side of the gantry, this occurred due to the radiation barrier wall (Pb ) not complete until the ceiling is only 2 meters high from the floor. The conclusion is that the walls of the Angiography/Cathlab room at Mitra Keluarga Kemayoran Hospital have exposure to skyshine radiation at a distance of 2 meters measured from the outer walls of the Angiography/Cathlab room on the west and north sides of the gantry of 0.32 µSv/hour and 0.39 µSv/hour. Keywords: angiography/cath lab, radiation, X-ray, skyshine, interventional radiology.

Analysis of Radiation Barrier Design in Peat Soil Using NCRP Method No.147 at Murjani Regional Hospital

The use of X-ray aircraft can hurt workers and the community, so they must pay attention to radiation protection aspects such as the design of radiation retaining walls which function to absorb and attenuate the resulting radiation exposure. This research was conducted to analyze the value of radiation exposure from radiology buildings on peat soil using the NCRP method No. 147. In this analysis, the rate of radiation exposure was measured using a Gamma Surveymeter, and the Pb thickness was calculated using the fitting and algebraic methods recommended by NCRP No. 147. Measurement and calculation of Pb are divided into 2 areas, namely controlled areas (Point B, Point C, and Point F) and uncontrolled areas (Point A, Point D, Point E, Point G, and Point H). The results of measurements and calculations from these eight protection points obtained radiation exposure rates in controlled areas at Point B (0.09 ?Sv/hour), Point C (0.04 ?Sv/hour), and Point F (0.03 (?Sv/hour ), and the results of calculating Pb thickness at Point B (0.07 mm), Point C (0.03 mm), and Point F (0.18 mm). Meanwhile, the rate of radiation exposure in uncontrolled areas at Point A (0.480 ?Sv /hour), Point D (0.068 ?Sv/hour), Point E (0.075 ?Sv/hour), Point G (0.41 ?Sv/hour), and Point H (0.45 ?Sv/hour), and the results of Pb thickness calculations at Point A (0.46 mm), Point D (0.08 mm), Point E (0.071 mm), Point G (0.038 mm), and Point H (0.005 mm). Based on these results, the radiation exposure rate value in controlled areas is still within safe limits, and in uncontrolled areas, the rate of radiation exposure that occurs is above the threshold of the dose-limiting value set by NCRP No. 147.

Proliferation aspects of partitioning and transmutation (P&T) fuel cycles

Abstract. Nuclear fuel is usually irradiated once but sometimes twice (MOX fuel). This procedure leaves a huge amount of spent fuel. Spent fuel is highly radioactive for a long time. Deep geological repositories are considered the best option for final disposal of this high-level radioactive waste. However, no such repository has been put into operation yet. Several countries consider partitioning and transmutation (P&T) a possible alternative. In P&T nuclear fuel cycles, the spent nuclear fuel is chopped into pieces and separated into different material streams such as plutonium, uranium and minor actinides. This process is called partitioning. From plutonium and minor actinides, new fuel elements are fabricated and used in nuclear reactors. If the overall physical conditions there are favorable, most prominently the presence of a fast neutron spectrum, at least a part of the minor actinides is fissioned and thus transmuted into other, hopefully easier-to-handle, nuclides. Especially when looking at the ingestion-based radiotoxicity index, reduction in minor actinides in nuclear waste is beneficial and might ease the requirements for a final repository. There are several drawbacks when looking at the concept of P&T: among others, several irradiation cycles are needed because the transmutation efficiency is so low. The technology for the processing of the spent fuel, the fuel fabrication and the irradiation is far from commercially available, and it is not clear whether this level can be met at all. This presentation focuses on the proliferation risk posed by possible P&T fuel cycles. The nexus between civil and military use of nuclear technology is widely known. If new fuel cycles are implemented, they should be more proliferation-resistant and not less. This would not be true for P&T fuel cycles: they require a closed nuclear fuel cycle with far more advanced reprocessing than today. Fissile material contained in spent nuclear fuel is not sent to final disposal but is separated into its components, which must be made available separately before they can be recombined into new fuel elements. Besides plutonium, this also includes other transuranic elements of small critical mass. The radiation barrier, an essential protection against unauthorized access to fissile material that could be used for nuclear weapons, is no longer present. The handling of those materials requires special facilities to cope with the immense amount of heat and radiation of the fuel containing high fractions of minor actinides. In those facilities, fissile material fitting for military purposes could be handled as well. Even if thorough safeguards are in place, detailed accountancy of all materials is not possible. The quantities needed to build a nuclear weapon are small compared to the quantities that need to be handled in a commercial-sized P&T fuel cycle. P&T technology is a civil application which clearly strengthens military capabilities. It would be hard to argue why it should only be available to a trustworthy partner (whoever that might be). The implementation of P&T fuel cycles would thus increase the risk of unauthorized diversion of nuclear material, technology and knowledge.

Janus Dual Self-Strengthening Structure of Bi2 O3 /Gd2 O3 Nanofibrous Membranes for Superior X-Ray Shielding.

Bi2 O3 /rare earth oxide biphasic absorbers are attractive for high-efficiency X-ray shielding due to the complementary X-ray absorption effects. However, its application is severely hindered by poor interphasic contact. Here, a new Janus interface engineering strategy is reported for the construction of continuous and flexible Bi2 O3 /Gd2 O3 crystal nanofibrous membranes (FJNMs) with micro/nano dual self-strengthening interphasic adhesion. This strategy facilitates online micro-interlocking between Bi2 O3 /Gd2 O3 nanofibers and in situ nano-grain fusion between Bi2 O3 /Gd2 O3 crystals, significantly enhancing the adhesive strength at the Bi2 O3 /Gd2 O3 interface. Additionally, the synergistic shielding effect from Bi2 O3 /Gd2 O3 absorption and multiple reflections in Bi2 O3 and Gd2 O3 crystal lattices make the nanofibrous membranes a superior X-ray radiation barrier. The FJNMs demonstrate integrated features of exceptional X-ray shielding efficiency (91%-100%), robust interfacial adhesion (lap-shear strength >3.8MPa), prominent flexibility, lightweight, and outstanding breathability. The design concepts of fibrosing biphasic absorber assemblies pave the way for asymmetrically assembling biphasic materials, setting the stage for a fundamental shift in next-generation radiation shielding materials.

Effect of MoO3 on Na2O–B2O3–CdO–ZnO glasses: Applications in optoelectronics, communication devices, and radiation shielding

The current study focuses on the physical and structural aspects of B2O3–CdO–ZnO–Na2O glasses that have been reinforced by MoO3 ions. The samples were experimentally prepared using a melt quenching procedure, and then the absence of strong peaks in the XRD spectra confirms their amorphous nature. A variety of optical, Raman, and radiationshielding qualities were evaluated and described. The structural changes in the material were investigated using FTIR and Raman spectra. The density of the samples rose when MoO3 was added, implying that BO3 was transformed into BO4 units. The transition of Mo6+ to Mo5+ ions is responsible for the reduction in band gap in these glasses. Because of the vacancy generated by the oxygen units, the Urbach energy increased, implying the generation of additional defects. The presence of diverse structures present in the structure of the glass was revealed by FTIR and Raman spectra, such as MoO6, BO3, BO4, metaborates, pyroborates, and so on. The transition of BO3 to BO4 units, which is crucial in density analyses, was also corroborated by Raman spectra. Using FLUKA simulation and XCOM estimations, the mass attenuation coefficient of the glasses improved with the amount of MoO3. At 15 keV, the half-value layer of 0.0103 cm, 0.01019 cm, 0.01016 cm, 0.0101 cm, and 0.01005 cm was obtained for glasses with an MoO3 concentration of 0, 0.5, 1, 1.5, and 2.0 mol% respectively. The optimum MoO3 concentration for fast and thermal neutron cross-sections was 0.5 and 2.0 mol% respectively. The glasses are viable materials for environmentally friendly and transparent radiation barriers in nuclear facilities.

Ultralow Emittance Thermal Radiation Barrier Achieved by a High-Contrast Grating Coating

Thermal radiative emission in vacuum is minimized using metal-backed flexible “space blankets” that have a theoretical minimum infrared emittance of 0.03. However, their presence under oxygenated and degradation-prone environments rapidly increases emittance due to metal oxidation, surface pitting, and implantation of contaminants. A monolithic dielectric coating composed of microscale periodic metasurface gratings on multilayers and metal thin film can achieve sub-1% total emittance. The minimum emittance can be tailored to any temperature-function blackbody emission, so long as the selected dielectric coating materials have near-zero absorption. Using computational optimization and theoretical understanding of high-contrast grating phase-shift mode conditions, we identified characteristic at-wavelength germanium gratings and a near-quarter-wave layer above a low-refractive-index infrared-transparent Fabry–Pérot multilayer interference cavity. This dual mechanism can achieve a room-temperature total emittance of 0.0085, paving a new theoretical minimum multilayer insulation effective conductance. As multilayer insulation, this coating offers total effective emittance of 0.0032 per pair of optimally mismatched grating surfaces. This ultrahigh reflection coating design can also be relevant in thermal management of refrigeration and electronic components.

ANALISIS PENAHAN RADIASI RUANGAN RADIOLOGI INTERVENSI CATHLAB SEBAGAI UPAYA PROTEKSI KESELAMATAN RADIASI DI RSUP. H. ADAM MALIK MEDAN

The exposure value received does not exceed the dose limit value (NBD) set by the regulation of the Nuclear Energy Supervisory Agency (BAPETEN) recommended by the National Council on Radiation Protection and Measurement (NCRP). This is the goal of radiation protection in achieving radiation safety for workers, patients and the public. To achieve this, it is necessary to evaluate the radiation-retaining structural walls of the interventional radiology room, X-ray fluoroscopy angiography, GE and Philips brands, Cathlab 1 and 2, respectively, at Adam Malik Hospital by comparing the data obtained from field calculations with the recommendations of regulators or theoretical. The results obtained are the thickness of the radiation retaining walls of the GE and Philips rooms by calculating the transmission factor and the thickness of the secondary radiation shield for each wall of the GE and Philips Cathlab rooms with a secondary air kerma value of 1 meter 3.8, the largest Xbarrier is 120.2 mm concrete, respectively. and 1.75mmPb and 81.13mmconcrete and 0.12mmPb. Using real calculations, the secondary air kerma value is 0.003 for the GE room, it is obtained that the concrete Xbarrier and Pb are minus values and the Philips air kerma value is 0.189, the Xbarrier is 22.1mm of concrete and 0.24mmPb. Meanwhile, the currently installed wall thickness is 28 cm of concrete and 0.5mmPb, with a total of 25 patients per week. On the other hand, exposure to environmental radiation, leakage of X-ray aircraft is also within safe limits. The conclusion is that the shield retaining installed both concrete and Pb on each wall of the X-ray inspection room of Cathlab 1 GE and Cathlab 2 Philips, Adam Malik General Hospital is in a safe condition for intervention, and radiation exposure measured in the environment as well as leakage of the light aircraft. -X is also within safe limits, so that the purpose of radiation shielding can be achieved, namely radiation exposure received by both officers, patients and the public does not exceed the specified dose limit value. Keywords: Radiation safety, dose limit value, radiation barrier, interventional radiology.

The Effectiveness of Bi2O3 Apron on Attenuation of X-Ray and Gamma Ray by MCNPX Simulation

Apron is one of the radiation shields, generally the apron used in radiodiagnostic installations is made of lead. However, lead aprons have disadvantages such as toxicity and relatively heavy weight. Therefore, it is necessary to innovate apron materials that are better than lead. This research was conducted by modelling an apron made of Bi2O3 with polyvinyl chloride as a coating and Pb as a standard apron. The used energies are 60, 90 & 120 keV for X-rays, 662 keV for Cs-137 (gamma ray), and 1173 and 1333 keV for Co-60 (gamma rays). The thickness of the radiation barrier is from 0.5 to 4 cm, and the distance of radiation source and detector is 45 cm. Bi2O3 apron geometry modelling was carried out using the MCNPX program. The modelling results show that at X-ray energy of 60 keV, the Bi2O3 apron can replace the Pb apron at a thickness of 1 cm to 4 cm. While at X-ray energy of 90 keV, the Bi2O3 apron can replace the Pb apron at a thickness of 2,5 cm to 4 cm, and at X-ray energy of 120 keV Bi2O3 apron can replace the Pb apron at a thickness of 1,5 cm to 4 cm. From these results it can be seen that the technology apron made from Bi2O3 with polyvinyl chloride as a coating with a certain thickness can be a non-lead radiation shielding material that is more environmentally friendly. But at the gamma energy of Cs-137 of 662 keV, Co-60 of 1173 keV and 1333 keV, Bi2O3 apron cannot replace Pb apron because the absorption of gamma rays is smaller than the absorption of X-rays. Keywords: Bi2O3 apron, X-ray attenuation, Gamma ray attenuation, MCNPX .

Nuclear proliferation resistance assessment of fuel cycles closed with complete co-processing of spent fuel

Purex (Plutonium Uranium Recovery by Extraction) is the standard reprocessing method used for the recovery of Uranium (U) and Plutonium (Pu) in spent fuel. Products of the standard reprocessing of spent fuel discharged from a typical LWR are separated and highly pure streams of U and Pu with fissile contents of roughly 0.85 wt.% (U-235 in U) and 70 wt.% (Pu-239+Pu-241 in Pu) respectively. Because of the economic and technological conditions and safeguard concerns, alternative methods or modifications for standard reprocessing including complete co-processing have been proposed. Complete co-processing is based on the Purex process and is an easier way of recovering U and Pu from spent fuel compared to standard reprocessing. In addition, since the U and Pu recovered together from spent fuel, it does not yield pure Pu and it is advantageous with regard to safeguards. The product obtained from complete co-processing of spent fuel is a U + Pu mixture with a total fissile content of around 1.5 wt% (U-235+Pu-239+Pu-241 in U + Pu), which is not suitable for direct use in LWRs and special approaches are required for recycling it. This study focuses on the assessment of nuclear proliferation resistance of fuel cycles closed with complete co-processing and different recycling scenarios for U + Pu product. To assess the proliferation resistance, intrinsic proliferation barriers including the amount of material to be diverted for significant quantity (SQ) of Pu, isotopic content of Pu, and radiation barrier of diverted material are compared for spent fuels generated in the cycles for one GWe-yr electricity production. To assess the impact of burnup on the proliferation resistance of cycles, all calculations are performed for the burnup values 33 GWd/tHM, 40 GWd/tHM, and 50 GWd/tHM. Results showed that the closed fuel cycle in which the U + Pu product from the complete co-processing is blended with 10 wt.% enriched uranium and recycled as mixed oxide fuel possesses the highest proliferation resistance. Besides, intrinsic nuclear proliferation barriers of all the fuel cycles investigated are positively affected by an increase in burnup.

CONVENTIONAL ROOM EFFECTIVENESS TEST USING RAYSAFE IN RADIOLOGY UNIT SITI RAHMAH ISLAMIC HOSPITAL PADANG

Siti Rahmah Islamic Hospital is a health service center in the city fields with a large number of patients. The more the number of patients, the greater the number the examination was carried out in the radiology room at the Siti Islamic Hospital Rahmah if the walls of the Radiology room are not effective, the dose will be receive to the patient, the patient's family and radiation staff will increase. This research aims to determine the effectiveness and level of security in conventional spaces Radiology Unit of Siti Rahmah Islamic Hospital against radiation with use raysafe unfors. This research was conducted by sticking raysafe unfors from the inside and the outside on walls, doors and Pb glass in a conventional room in the Hospital Radiology Unit Islam Siti Rahmah with the type of quantitative research. The results of the measurement of the largest dose rate were found at the inner 3A point, which was 10.5198 mGy/h. While the results of the measurement of the smallest dose rate are at the outer 7B point, which is -0.0001 mGy/h. The dose before penetrating the material (D0) measured in a conventional room ranged from 10.5198 –1.3228 mGy/h. The dose value that varies at the measurement point is caused by the distance of the radiation source from the measurement point. Where in the conventional room (D0), the largest measured radiation dose is at point 3A 10.5198 mGy/h. This is because the measurement position is closest to the radiation source with a distance of 160 cm. Conventional space buildings are already effective against scattered radiation and safe as a radiation barrier with the effectiveness of values ranging from 99.9% to 100%. The results showed that the ability of walls, doors and Pb in a conventional room in the Radiology Unit of the Siti Rahmah Islamic Hospital absorb radiation.

Fabrication, thermal analysis, and heavy ion irradiation resistance of epoxy matrix nanocomposites loaded with silane-functionalized ceria nanoparticles

This paper describes a detailed understanding of how nanofillers function as radiation barriers within the polymer matrix, and how their effectiveness is impacted by factors such as composition, size, loading, surface chemistry, and dispersion. We designed a comprehensive investigation of heavy ion irradiation resistance in epoxy matrix composites loaded with surface-modified ceria nanofillers, utilizing tandem computational and experimental methods to elucidate radiolytic damage processes and relate them to chemical and structural changes observed through thermal analysis, vibrational spectroscopy, and electron microscopy. A detailed mechanistic examination supported by FTIR spectroscopy data identified the bisphenol A moiety as a primary target for degradation reactions. Results of computational modeling by the Stopping Range of Ions in Matter (SRIM) Monte Carlo simulation were in good agreement with damage analysis from surface and cross-sectional SEM imaging. All metrics indicated that ceria nanofillers reduce the damage area in polymer nanocomposites, and that nanofiller loading and homogeneity of dispersion are key to effective damage prevention. The results of this study represent a significant pathway for engineered irradiation tolerance in a diverse array of polymer nanocomposite materials. Numerous areas of materials science can benefit from utilizing this facile and effective method to extend the reliability of polymer materials.

Radiation Attenuation Ability of Bentonite Clay Enriched with Eggshell as Recyclecable Waste for a Physical Radiation Barrier

Radiation Attenuation Ability of Bentonite Clay Enriched with Eggshell as Recyclecable Waste for a Physical Radiation Barrier