Periódicos

URI Permanente para esta coleçãohttps://repositorio.ipen.br/handle/123456789/3977

Navegar

Agora exibindo 1 - 20 de 8095

Recent results on the analysis of the 48Ti(18O, 17O)49Ti reaction at 275 MeV
2024 - SGOUROS, O.; CAPPUZZELLO, F.; CAVALLARO, M.; CARBONE, D.; AGODI, C.; BRISCHETTO, G.A.; CALVO, D.; CHAVEZ LOMELI, E.R.; CIRALDO, I.; CUTULI, M.; DE GREGORIO, G.; DELAUNAY, F.; DJAPO, H.; EKE, C.; FINOCCHIARO, P.; FISICHELLA, M.; GARGANO, A.; GUAZZELLI, M.A.; HACISALIHOGLU, A.; LINARES, R.; LUBIAN, J.; MEDINA, N.H.; MORALLES, M.; OLIVEIRA, J.R.B.; PAKOU, A.; PANDOLA, L.; SOUKERAS, V.; SOULIOTIS, G.; SPATAFORA, A.; TORRESI, D.; YILDIRIM, A.; ZAGATTO, V.A.B.
The study of the one-neutron transfer reaction in the 18O+48Ti collision at the energy of 275 MeV was performed as part of the multi-channel approach which is performed within the NUMEN project. That is to measure the complete reaction network characterized by the same initial and final state interactions as the more suppressed double charge exchange reactions. In this respect, angular distribution measurements for one- and two-nucleon transfer reactions in the 18O+48Ti collision were performed at the MAGNEX facility of INFN-LNS in Catania. This contribution summarizes the main findings from the analysis of the one-neutron transfer reaction.
Pressure vessels structural integrity assessment using failure analysis diagrams
2025 - ROCHA PINTO, J.J.; MATTAR NETO, M.
There is much discussion today about the possibility of extending the lifetime of industrial plant components due to economic factors. Pressure vessels are among the most expensive components, and their replacement can significantly impact the operation of an entire plant. In this context, several Fitness-for-Service (FFS) methodologies can be applied to assess structural integrity, addressing not only economic aspects but also enhancing safety. Failure Assessment Diagrams (FADs) are widely used in FFS methodologies to prevent future failures by analyzing crack-type defects. These diagrams establish acceptability criteria based on the material toughness ratio and loading ratio. Recommended practices utilizing the BS-7910, API-579, and R6 methodologies are addressed in this work, alongside principles from fracture mechanics, material properties, and solid mechanics. The main objective was to develop computer programs in Matlab to analyze a case study involving a pressure vessel manufactured from SA-516 Gr 70 steel, determining the critical dimensions of semi-elliptical cracks in longitudinal and circumferential orientations of a cylindrical section. Level 2 evaluation, the most commonly used in FFS methodologies, was applied to develop the programs. This study enabled the creation of tools to automate calculations and generate FAD graphs, considering the critical depth and length of cracks. These tools support decision-making in structural design requirements and provide a means of evaluating equipment in service with crack-type defects, extending its operational lifetime. The FFS methodologies studied are based on ASME Codes for pressure vessels and piping, particularly Sections III and XI. Based on the analysis of API-579, BS-7910, and R6 methodologies under the operating conditions of the case study, it is possible to conclude that, for normal evaluations, critical length (2c) = 40.64 mm and critical depth (a) = 10.16 mm are acceptable values. However, for evaluations requiring safety considerations under the R6 procedure, applicable to Class A service equipment in the nuclear sector, only critical length (l) = 5 mm and depth (a) = 2.5 mm are permissible values.
Development of a sample exchange system for irradiations in the BH-3 channel of the IEA-R1 reactor at IPEN
2024 - PAULA, M.L. de; MORALLES, M.; GENEZINI, F.A.; SIQUEIRA, P.T.D.; RIBEIRO JUNIOR, I.S.; SILVA JUNIOR, I.A. da
This work was developed with the aim of improving the current sample exchange system of the BH-3 irradiation channel of the IEA-R1 reactor at IPEN. The instrument's operating concept will provide a better use of the irradiation space as well as greater safety and confidence to the operator. The development of the system involved 3D modeling, sizing, construction and non-destructive testing of the various parts, and analysis of neutron-induced activation of the materials most exposed to the beam. A programmable logic controller (PLC) was implemented for the system’s control inside a dedicated electrical panel that was built with materials compatible with the location. The system was designed to support samples weighing up to 15 kg. Bench tests were carried out and showed that the system performs the necessary functions to accurately position samples in three locations: outside the biological shield, at the irradiation channel and at the decay waiting station. The implementation of this instrument will contribute to the application of the ALARA principle in the operator activities at the BH-3 irradiation channel.
Study on the licensing framework for land facilities supporting nuclearpowered submarines in the United Kingdom
2024 - BARONI, D.B.; BORSOI, S.S.; SOARES, Y.S.A.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.
This study examines nuclear regulation in the United Kingdom, focusing on licensing processes for land facilities supporting nuclear-powered submarines. It highlights the importance of these submarines for defense and maritime security, along with the need for specialized infrastructure to operate them safely and effectively. The study analyzes the UK’s procedures and regulations for nuclear licensing, with emphasis on regulatory bodies such as the Office for Nuclear Regulation (ONR) and the Defence Nuclear Safety Regulator (DNSR). Results discuss the classification of nuclear facilities in the UK, including those dedicated to submarines and nuclear defense, as well as the applicable standards and guidelines for licensing these facilities. It is concluded that nuclear regulation in the UK is robust and transparent, providing a solid foundation for licensing facilities supporting nuclear-powered submarines. The adoption of these standards as a reference in Brazil could significantly contribute to establishing a solid and secure regulatory framework for such facilities.
Impact of distinct sintering temperatures in pellets to strontium immobilization
2024 - SANCHES, G.O.P.; ARAUJO, M.S.; MELLO-CASTANHO, S.R.
The immobilization of radioactive strontium (Sr) from liquid effluents, a byproduct of nuclear fission and accidents, presents significant environmental and public health challenges. This study evaluates the immobilization of Sr in a glass matrix by comparing the effects of different sintering temperatures. The analyses started from three temperatures 800ºC, 900ºC and 1000ºC for each of the four compositions, which vary the addition of niobium (Nb) content in the vitreous matrix by 2%, 4%, 6% and 8% in mol. The highest temperature was excluded because its deformation did not match the final objective, at 900ºC the compositions had better results in density and water absorption, so that at the same temperature the composition with 4% niobium responded better to the results. The study underscores the significance of treating temperature and Nb content in the glass matrix for effective Sr immobilization, offering valuable insights for the development of safe and sustainable nuclear waste management strategies.
Thermal evaluation of a Cs-loaded waste vitrification
2024 - COSTA-SILVA, D.L.; ARAUJO, M.S.; FUNGARO, D.A.; MELLO-CASTANHO, S.
Nuclear power generation has been increasing worldwide over the years, helping to avoid the emission of billions of tons of carbon dioxide (CO2) compared to coal power generation, making it a reliable method for providing green energy. However, as a byproduct of nuclear reactors, as well as fuel processing plants, hospitals, and research institutes, radioactive waste is generated. These wastes pose a significant risk to human health and the environment due to the penetration of radioactivity into tissues, which damages DNA. Therefore, they need to be managed appropriately before long-term disposal in geological repositories. Among the many radionuclides found in high-activity waste, 137Cs is of particular concern due to its high mobility in water systems, requiring special methods for its capture and immobilization in stable matrices. In this study, the immobilization of 137Cs radionuclides in a borosilicate glass doped with niobium (Nb) was thermally evaluated through a vitrification process, using a synthetic type A zeolite saturated with 133Cs (stable) as a simulated radioactive waste. The incorporation of 40.0 wt.% of this material into the glass composition resulted in a vitrified waste with good melting homogeneity and thermal stability. Several changes due to the incorporation were detected in thermal analysis (DTA), with events such as glass transition, initial crystallization, complete crystallization, and subsequent melting all shifting to higher temperatures. The compositional changes induced by vitrification moved the system to new locations in the ternary equilibrium phase diagrams of the subsystems, in different compatibility triangles, and closer to higher liquidus temperatures than those observed for the raw glass matrix. Through crystallization induced by heat treatment, crystalline phases were obtained, as indicated in the phase diagrams. Cs atoms previously immobilized in the glass network structure became components of pollucite crystals (CsAlSi₂O₆) during heating up to 800 ºC. These results are promising for using this glass composition to immobilize waste containing 137Cs, as Cs atoms showed excellent interaction with this system in both the glass and crystalline phases.
Accumulated dose stability parameters in p-type and n-type silicon diodes
2024 - PASCOALINO, K.; GONCALVES, J.A.C.; CAMARGO, F.; BUENO, C.C.
This work investigates the influence of doping type on the dose responses and the accumulated dose stability of n- and p-type silicon MCz diodes. The operating principle of diode-based dosimeters relies on measuring the radiation-induced currents delivered by non-polarized diodes throughout the exposure time. An electrometer promptly reads the current signal, linearly dose rate dependent. The offline integration of the current signal provides the charge generated in the sensitive volume of the diode, expected to be proportional to the absorbed dose. The experimental approach involves analyzing the repeatability of the current signals, the dose responses of both pristine and pre-irradiated diodes, the correspondent charge sensitivities, and the sensitivity decay with increasing doses. For doses up to 175 kGy, the results reveal a linear dose response of the MCz(p) diode, characterized by a charge sensitivity of 3.1 µC/Gy. Within the same dose range, the response of the MCz(n) diode is visibly saturated and given by a fourth-order polynomial function. This saturation effect is likely linked to radiation damage effects manifesting in the current decay with increasing accumulated doses. This surmise is confirmed in this work by a less pronounced drop in sensitivity of the p-type diode than that recorded for the n-type diode when both are subjected to 175 kGy. This behavior is ascribed to the working principle of the diode in the short-circuit current mode and the differences between the diffusion lengths of minority carriers in n- and p-type silicon materials. The diodes' response stability and dose lifespan remain to be further investigated.
A dosimetric evaluation using the Monte Carlo method considering geometric variations of the Iodine-125 seed for brachytherapy
2024 - CHICO, H.S.; ANGELOCCI, L.V.; ZEITUNI, C.A.; SOUZA, C.D.; SGRIGNOLI, S.S.; ROSTELATO, M.E.C.M.
The Institute for Energy and Nuclear Research – IPEN-CNEN/SP is uniquely positioned to develop a new source of Iodine-125 for brachytherapy treatment. Therefore, research into the dosimetric process and source design is widely studied. Task Group 43 – TG 43 cites methodologies for dosimetry of sources for brachytherapy, the most used method is Monte Carlo. However, the dosimetric protocol does not mention possible variations in the source geometry after its conception. The investigative focus of the work was to obtain measurements of the Iodine-125 seed during the production stages until completion, quantify them and simulate them using the Monte Carlo method with the MCNP – 4C code, the formalism was in water and a 101x101 matrix was used to calculate the dose point by point. Two variations were chosen: a) seed length; b) nucleus length, using a batch of 100 seeds for each case. 100 simulations were carried out for each variation and one simulation using the reference seed geometry. The following calculations were applied: relative difference to compare variations to the reference; average among the 100 seeds of each batch to calculate the standard deviation. In both cases there was no point that exceeded 4.48% relative difference, and for standard deviation the largest point was 1.6%, while the Type A uncertainty was 0.018% at the largest point.
Conservation of bibliographic collections using gamma ionization
2024 - BRITO, S.G.; OLIVEIRA, M.J.A.; SALVADOR, P.A.V.
The preservation of cultural assets, especially bibliographic collections, requires the dissemination of the gamma ionization technique, which is mainly used for the decontamination and sterilization of these materials. The procedure, which is used to preserve library collections in Brazil and other countries, is also used to preserve documents and art collections, being safe to handle, after ionization, once it leaves no residue behind. The aim of the study was to assess knowledge and identify behavioral aspects related to gamma ionization and its application in decontaminating collections. The target audience was a group of professionals who work with cultural assets in Pernambuco and other states. Two questionnaires were used, obtaining 39 and 105 respondents respectively, characterizing the participants and their knowledge of gamma ionization. The research was qualitative and quantitative, of a phenomenological nature. For the analysis, questions were grouped into thematic blocks, characterizing the participants, finding out “knowledge of gamma ionization itself” – with both knowledge and ignorance of the concept and application of the technique – and also collecting from participants their feelings, opinions and positions on various aspects of the application of gamma ionization. Finally, means and personal sources of obtaining information were specified, dealing with sharing of information.
Dosimetry for FLASH radiotherapy
2024 - SUZART, K.F.; POTIENS, M.P.A.
FLASH radiotherapy (FLASH-RT) is a promising approach to cancer treatment, characterized by the delivery of high doses of radiation in a short period of time, within fractions of seconds. In order to demonstrate the FLASH effect, single high doses of radiation delivered in very short times through a limited number of pulses are required. Previous studies have reported that FLASH-RT treatment can result in increased cell survival compared to conventional radiotherapy. This article aims to conduct a comprehensive literature search on dosimetry in FLASH radiotherapy, an emerging and promising technique in the field of radiotherapy. Some of the most used dosimeters in recent studies for FLASH radiotherapy will be discussed, including ionization chambers, diamond detectors, radiochromic films, EBT3 radiochromic films and thermoluminescent dosimeters. The main dosimetry parameters used in FLASH radiotherapy treatments will be analyzed, with emphasis on the characteristics and applicability of the different types of dosimeters used.
Effects of ionizing radiation on artistic paints and pigments used in the restoration of works of art
2024 - ANTONIETTO, H.P.; OLIVEIRA, M.J.A.; ARAUJO, M.S.; OTUBO, L.; MELLO CASTANHO, S.R.; VASQUEZ, P.A.S.
Ionizing radiation is an alternative in combating the deterioration of cultural heritage as it is effective in eliminating biological infestations, from the presence of insects to contamination by fungi and bacteria. The process took place through the emission of gamma radiation (60 Co). The objects of study refer to 3 samples of canvas that received layers of paints and pigments, both intended for the practice of restoring works of art and that were exposed to cumulative doses of 3 to 15 kGy. Instrumental analyzes included X-ray Fluorescence Spectroscopy – XRF, Colorimetry, Scanning Electron Microscopy - SEM and Fourier Transform Infrared Spectroscopy - FTIR. The results of the analyzes showed that the samples remained without significant changes.
Byproduct-based zeolite type A as absorbent material for decontamination of simulated radioactive wastewater
2024 - ARAUJO, M.S.; COSTA-SILVA, D.L.; MELLO CASTANHO, S.R.; FUNGARO, D.A.
The secure disposal of radioactive wastewater, a waste from nuclear operations, presents a significant challenge due to the presence of hazardous radionuclides like cesium. The efficient removal of cesium, a major fission product with a long half-life and potent radiation, is crucial for environmental and human health protection. Zeolites, with their high ion exchange capacity and porous structure, offer a promising solution for cesium removal from wastewater. The potential to synthesize zeolites from abundant and cost-effective agro-industrial residues further enhances their appeal for sustainable wastewater treatment. The present study investigates the adsorption of cesium from simulated radioactive wastewater using zeolite type A synthesized from sugarcane bagasse ash, a readily available Brazilian byproduct. The synthesized zeolite was characterized by X-ray fluorescence spectroscopy, X-ray diffraction, and thermal analysis techniques. The results confirmed the successful synthesis of high-purity zeolite A with excellent adsorption capacity for cesium. The structural integrity and thermal stability of the zeolite were maintained even after cesium adsorption, making it suitable for immobilization processes. The findings highlight the potential of zeolite synthesized from sugarcane bagasse ash as an effective and sustainable material for the treatment and removal of cesium from radioactive wastewater, contributing to environmental remediation efforts in the nuclear industry.
Potential of ionizing radiation application for reducing environmental risks related to solids residues
2024 - BORRELY, S.I.; VOGT, M.V.; AQUINO, S.; GARCIA, V.S.G.; PACHADO, J.
The enormous amount of solids residues and related cost for a suitable disposal have increased in megacities as São Paulo and Buenos Aires. Inovative technologies may be used in order to face managing progams with inovative techniques for for recycling or recover of materials. Gamma radiation was applied in laboratory scale for two different types of residues: fungi control in vehicular air filters, and for rat bedding waste (RBW) disinfection. Both materials may be used after irradiation and the radiation doses required will be discussed. Part of experiments carried out in Argentina evidenced the suitable use of vermicomposting for growing Calendula officinalis. Radiation doses from 10 kGy up to 30 kGy were tested for controlling microorganisms during the projects and were very effective. For filters disinfection experiments, DNA sequencing analysis for the fungi that survived after irradiation not only confirmed the presence of Penicillium, Fusarium and Aspergillus (toxigenic), fungi but also improved the data: the contamination included Aspergillus niger, Aspergillus flavus, Penicillium glabrum specie complex and Fusarium incarnatum-equiseti specie complex.
Polymeric membranes grafted by ionizing radiation for uranium adsorption
2024 - CARDOSO, A.C.P.; GARCIA, R.H.L.; CARVALHO, E.F.U. de; AL SHEIKHLY, M.; KODAMA, Y.
Fuel elements production by IPEN-CNEN has a perspective to be increased to attend Brazilian Multipurpose Reactor, under construction. This production generates liquid waste that requires proper treatment to minimize environmental impacts, promoting more sustainable practices. Considering the rise on nuclear power energy generation, and that there is global lack of terrestrial uranium sources, the increasing demand for this element has been leading to uranium exploit alternatives. So, several researches are available on uranium adsorption from sea water. Adsorption is one of process for removing metals from wastewater, due to its high selectivity and low environmental impact. Taking into account this scenary, in this study, Winged Polypropylene (WPP) fabric was grafted via ionizing radiation (RIG) with the monomer Bis[2-(methacryloyloxy) ethyl] phosphate (B2MP). RIG promotes functionalization of WPP with phosphate groups that are prone to capture U from solution. Synthesized WPP-g-polyB2MP membranes were characterized by Scanning electron microscopy (SEM), Raman spectroscopy, thermogravimetry and, uranium adsorption capacity by ICP-OES and gamma spectrometry. WPP-g-polyB2MP membranes were successfully synthesized by ionizing radiation grafting direct method. Reaction parameters, like reactants concentration, radiation absorbed dose, affected the degree of grafting (DoG). By physico-chemical characterization results it was possible to observe DoG differences with parameters variation. Optimization of these parameters was sought in order to achieve uranium adsorption, and to increase the adsorption capacity of the membrane.
Soluble polymer-curcumin encapsulation to protect against gamma irradiation and increase the water solubility
2024 - ALMEIDA, L.D.; PARRA, D.F.
Curcumin is a polyphenol derived from turmeric, a herbaceous plant native from Asia, which has been studying for medicinal properties. Over the years, different civilizations have used those plants to treat or prevent bacterial diseases. Technological advances have made it possible for scientists to study the activity mechanisms, as well as properties derived from these mechanisms, known as medicinal plants. These studies have confirmed that turmeric's medicinal properties are derived from its polyphenols, which in turn can be identified, isolated and used more efficiently. Despite curcumin's antimicrobial benefits, its highly hydrophobic molecule affects its use in biological systems, as well as its bioavailability in humans and animals. The process of modifying a molecule allows changes to be made to its characteristics, benefiting its use; in this context, encapsulation with polymers with amphiphilic characteristics, such as PVP K30, presents itself as a viable alternative for greater affinity with biosystems. The encapsulate curcumin, called C-PVP K30, proved to be possible and effective, keeping the molecule stable and in nanometric dimensions, based on results from DLS and ZETA analyses. Microscopy analysis (SEM-FEG) showed morphologically spherical and dispersed particles with small points of agglomeration. The successful encapsulation of this active substance allowed the solution to be studied under gamma radiation. The results obtained by FTIR and UV-Vis show that this process was unable to protect the curcumin molecule against ionizing radiation.
Soft Systems Methodology as an approach to the safety management of nuclear facilities
2024 - GUILHEN, S.N.; CAMARGO, I.M.C.; POTIENS JUNIOR, A.J.; MARUMO, J.T.; SILVA, T.M. da; RUBIN, G.A.; VIEIRA NETO, A.S.
This manuscript presents an account of the Sociotechnical Systems Safety Analysis Group’s (GASSST) application of Soft Systems Methodology (SSM) to a complex safety issue at the Nuclear and Energy Research Institute in São Paulo, Brazil (IPEN-CNEN/SP). Drawing from both theoretical foundations, based on the documentation produced by Peter Checkland and other researchers, and practical experiences, the study explores the SSM approach in addressing challenges that involved technical and human factors. The principal results include the identification of key stakeholder perspectives, the development of a rich picture to capture the complexity of the problem, and the initiation of potential solutions. However, the full application of SSM was curtailed due to proactive interventions by the facility staff, which resolved the initial problem before all SSM steps could be completed. The process was further interrupted by the COVID-19 pandemic-induced hiatus, during which facility staff were absent for 1 year and 10 months. The study concludes that timely application of SSM and the expertise of facilitators are critical for navigating complex safety issues effectively. This experience underscores the need for experienced practitioners and a more prompt application of SSM to fully leverage its potential in addressing organizational challenges. GASSST's reflections and documented experiences contribute valuable insights to the ongoing discourse on SSM's practical relevance in similar contexts.
Restoration of culturally significant wooden artifacts using gamma radiation curable polyester resins
2024 - PEREIRA, M.A.M.G.; OLIVEIRA, M.J.A.; OTUBO, L.; FERNANDES, V.; VASQUEZ, P.A.S.
The preservation of cultural artifacts, particularly those made of wood, is a significant concern for conservators due to their susceptibility to damage from xylophagous organisms, fungi, and bacteria. This study investigates the use of gamma radiation to cure polymeric resins for the consolidation of three wood species: cedar (Cedrela spp.), canafistula (Peltophorum dubium), and ivorywood (Balfourodendron riedelianum). Various resins, including polyester LP 8847® combined with styrene, were subjected to gamma radiation to induce cross-linking without the need for catalysts. The results demonstrated that gamma radiation effectively cured the resin, filling wood pores and enhancing structural integrity. The analysis of apparent density showed that cedar, canafistula, and ivorywood exhibit different absorption capacities, with cedar absorbing the most resin and canafistula the least. Optical and Scanning Electron Microscopy confirmed the efficient penetration of resin into the wood samples, indicating that gamma radiation can be a viable technique for wood consolidation and protection against degrading agents.
Preserving cultural heritage through radiation-curing resin consolidation
2024 - DELGADO VIEIRA, A.C.; VASQUEZ, P.A.S.; OLIVEIRA, M.J.A.; SILVA, F.A.
This article presents a case study on a ceramic vessel belonging to the Amazonian indigenous people, Asurini do Xingu, to investigate the use of gamma radiation for consolidating cultural heritage. Traditionally, gamma radiation is used to impregnate cultural artifacts with a radiocurable resin. In this study, the consolidating resin was applied only to the external surface of the vessel by brushing. The object was weighed before and after consolidation, and a colorimeter was used to evaluate possible color changes. The results indicated that the method was effective, with no negative effects on the appearance of the cultural item.
Paraloid resins with polymeric monomers cured by gamma radiation for consolidation of porous wood
2024 - OLIVEIRA, M.J.A.; ARAUJO, M.; OTUBO, L.; CASTANHO, S.M.; VASQUEZ, P.A.S.
Preservation consists of an action that aims to guarantee the integrity and perpetuity of something, such as a cultural asset. One of the preservation instruments is restoration, an intervention that aims to definitively secure a product of human activity. Cultural heritage presents an extensive diversity of wooden objects, which can be affected by insect attacks, causing severe damage to their structures. To recover this damage, compatible materials are needed to maintain their integrity. Therefore, we propose to study the obtaining of polymeric resins cured by gamma radiation without the use of catalysts for consolidation or restoration of wooden objects. A series of formulations were developed with polymeric resins based on paraloid B72 and polymeric monomers cured by gamma radiation from a cobalt-60 source. These resins were characterized by physicochemical analyses, and the results presented were surprising in terms of reversibility. Gamma radiation replaced the catalyst, curing the resin 100%, indicating new resin options for restoration and/or consolidation in porous wood.
Material imaging study of 3D printing materials for diagnostic radiology phantom development
2024 - OLIVEIRA, M.V.L.; SAVI, M.; VITOR, A.; VILLANI, D.; ANDRADE, M.A.B.; UBEDA, C.; MITSUO, M.M.
The 3D printing techniques have found applications across diverse fields, significantly enhancing design and manufacturing processes. The impact of this growth is particularly notable in radiology, where 3D printing has been applied to developing quality control tools and advancing dosimetry techniques. 3D printing has the advantage of having a wide variety of plastic materials which can be used in the manufacturing process; there is a scarcity of work developed to evaluate the attenuation of the x-ray beam of the materials used in printing 3D models for phantom development. This paper aims to show our results on the imaging characteristics investigation of 15 3D printable materials. 3D objects were printed as cubes of 20 x 20 x 20 mm3 with a 100% infill and 45°/45° rectilinear structural pattern, and images acquired in a DR X-ray unit were analyzed with ImageJ software. Imaging pixel values, Signal-to-Noise Ratio – signal-to-noise ratio and Contrast-to-Noise Ratio – contrast-to-noise ratio were evaluated and compared between the 3D-printed cubes and a standard chest phantom. When comparing the SIGNAL-TO-NOISE RATIO for plastic materials and chest structures, significant differences were found. Similar results were found for the contrast-to-noise ratio. The differences were noted by the use of Kruskal Wallis test for both plastic materials, Tungsten and Bismuth, that demonstrated statistically significant values of signal-to-noise ratio compared to the lung (p < 0.0001) and right rib (p < 0.0001). Tungsten and Bismuth filaments were found to have the potential to represent the signal-to-noise ratio for intermediary and high-density structures. Scapula was the only anatomical structure with no statistically significant difference of the contrast-to-noise ratio for SILK (p ≥ 0.074), ABS (p ≥ 0.086), PVA (p ≥ 0.917) and ABSpremium (p ≥ 0.955). The study of potential radiological 3D printing materials for diagnostic radiology phantom development revealed important imaging characteristics for the plastic materials using the Fused Filament Fabrication technique.

Navegar

Submissões Recentes