Nuclear Medical Applications Research Articles

Steps of Exact and Analytic Solutions of Ordinary Differential Equations using MAHA Integral Transform and Its Applications

Transformation such as integral transform is needed to obtain the exact solutions for linear ordinary differential equations (ODEs) with constant coefficients of higher orders. MAHA transformation exact solution of ODEs is simpler and easier than the previous with two parameters. The major steps of this transform are applying the MAHA transform on the given equation followed by taking the inverse transform. The general steps in numerical solutions involve defining the ODE as a function, defining initial conditions and the range of the independent variable, using an appropriate ODE solver function, and calling the solver and plotting the solution using a programming language. The exact and analytical solutions are validated. Both methods are easy and simple to be deployed in computing scientific applications such as nuclear physics and medical applications.

A comprehensive review of sensors of radiation-induced damage, radiation-induced proximal events, and cell death.

Radiation, a universal component of Earth's environment, is categorized into non-ionizing and ionizing forms. While non-ionizing radiation is relatively harmless, ionizing radiation possesses sufficient energy to ionize atoms and disrupt DNA, leading to cell damage, mutation, cancer, and cell death. The extensive use of radionuclides and ionizing radiation in nuclear technology and medical applications has sparked global concern for their capacity to cause acute and chronic illnesses. Ionizing radiation induces DNA damage either directly through strand breaks and base change or indirectly by generating reactive oxygen species (ROS) and reactive nitrogen species (RNS) via radiolysis of water. This damage triggers a complex cellular response involving recognition of DNA damage, cell cycle arrest, DNA repair mechanisms, release of pro-inflammatory cytokines, and cell death. This review focuses on the mechanisms of radiation-induced cellular damage, recognition of DNA damage and subsequent activation of repair processes, and the critical role of the innate immune response in resolution of the injury. Emphasis is placed on pattern recognition receptors (PRRs) and related receptors that detect damage-associated molecular patterns (DAMPs) and initiate downstream signaling pathways. Radiation-induced cell death pathways are discussed in detail. Understanding these processes is crucial for developing strategies to mitigate the harmful effects of radiation and improve therapeutic outcomes.

Excitation functions for [formula omitted]Ag(α,x) reactions with detailed covariance analysis

Excitation functions for [formula omitted]Ag(α,x) reactions with detailed covariance analysis

Design and beam dynamics validation of a spiral FFAG accelerator for CSNS-II

The fixed-field alternating gradient (FFAG) accelerator, with its compact structure and the combined advantages of high energy from synchrotrons and high beam intensity from cyclotrons, offers unparalleled benefits in accelerating protons, heavy ions, and short-lived particles such as muons and unstable nuclei. The China Spallation Neutron Source plans to establish an FFAG accelerator with a diameter of 20 meters at the end of the negative hydrogen linac for various purposes, including experiments in nuclear physics and medical applications. For this design, a scaling scheme using spiral magnets as the basic focusing structure is investigated to provide the proton beam with kinetic energy ranging from 300 MeV to 600 MeV. We present the design results for the scaling FFAG accelerator and discuss the optimization of the cell tune. A detailed beam dynamics verification and discussion of the proposed FFAG accelerator lattice are presented using the ray-tracing code Zgoubi, including off-axis optical characteristics, large amplitude transverse motion, and full-cycle longitudinal acceleration. The FFAG accelerator is demonstrated to provide a large transverse and longitudinal acceptance for the tracking beam in the designed lattice. A new simulation code based on Python for the study of FFAG accelerator beam dynamics has been developed, and the corresponding verification results are also presented.

AI in Nuclear Medical Applications: Challenges and Opportunities

The Article Abstract is not available.

Characterization of plastic scintillator samples produced by a university-SME Collaboration

Scintillator samples are synthesized by a university-SME collaboration and the light yield, light emission and light transmission properties are studied with the aim of determining the fluor content that gives the highest light yield. Three plastic scintillator samples with different fluor additives are produced and their optical properties are found to be comparable with a high-light-yield EJ-204 reference sample. Amongst the three, the sample with 0.75% PPO + 0.75 %PTP and 0.04% POPOP + 0.04% Bis-MSB provides the highest light yield. The authors plan to use the same fluor additive concentration to produce application-specific scintillators that are not commercially available for nuclear reactor monitoring and medical applications.

Highlights and outlook of the Dutch PIONEER 2021–2024 R&D program

Highlights and outlook of the Dutch PIONEER 2021–2024 R&D program

Isotopic dependence of (n,α) reaction cross sections for Fe and Sn nuclei

Isotopic dependence of (n,α) reaction cross sections for Fe and Sn nuclei

Physics at the Legnaro National Laboratories: present activities and future challenges

The Legnaro National Laboratories are one of the four INFN laboratories and they are mainly dedicated to experimental nuclear physics and astrophysics, within the field of nuclear structure and dynamics, where heavy ion induced reactions at medium-low energies are involved. Moreover, high level technologies for the construction of particle accelerators and experimental instruments and apparatuses are studied and developed. The laboratory is at present involved in the construction of the SPES facility, which concerns the development of a new research infrastructure devoted to the production of exotic beams for nuclear physics study and new radioisotopes for nuclear medical applications. The heart of SPES is an innovative cyclotron, B70, capable of providing high intensity proton beams (up to 750 μA) in the energy range between 35 and 70 MeV. A description of the present and future challenges at the Legnaro National Laboratory will be given.

Low energy radioactive ion beams at SPES for nuclear physics and medical applications

Over the past decades many accelerator facilities have been built in order to produce radioactive nuclei. Among the falcility under construction, SPES (Selective Production of Exotic Species) is the Italian ISOL (Isotope Separation On Line) facility in the installation phase in these years in the Laboratori Nazionali di Legnaro. The innovative aspect of this facility is that the radioactive beam produced by fission induced by the proton beam, produced by a high power cyclotron, interact with a multi-disks uranium carbide target. The formed RIB will be sent directly to the low energy experimental area and, afterwards, to the post-acceleration complex. Currently the installation program concerning the SPES RIB source provides the set-up of the apparatus around the production bunker. The main objective of SPES project is to provide, in the next years, the first low-energy radioactive beams for beta decay experiments using the b-DS (beta Decay Station) set-up and for radiopharmaceutical applications by means of the IRIS (ISOLPHARM Radioactive Implantation Station) apparatus. In this work, all the specific issues related to the SPES RIB and the Low Energy beam lines will be reported. The main RIB systems, such as ion source systems, target-handling devices and the installation of low energy transport line, will be presented in detail.

A framework for prediction of personalized pediatric nuclear medical dosimetry based on machine learning and Monte Carlo techniques

Objective: A methodology is introduced for the development of an internal dosimetry prediction toolkit for nuclear medical pediatric applications. The proposed study exploits Artificial Intelligence techniques using Monte Carlo simulations as ground truth for accurate prediction of absorbed doses per organ prior to the imaging acquisition considering only personalized anatomical characteristics of any new pediatric patient. Approach: GATE Monte Carlo simulations were performed using a population of computational pediatric models to calculate the specific absorbed dose rates (SADRs) in several organs. A simulated dosimetry database was developed for 28 pediatric phantoms (age range 2–17 years old, both genders) and 5 different radiopharmaceuticals. Machine Learning regression models were trained on the produced simulated dataset, with leave one out cross validation for the prediction model evaluation. Hyperparameter optimization and ensemble learning techniques for a variation of input features were applied for achieving the best predictive power, leading to the development of a SADR prediction toolkit for any new pediatric patient for the studied organs and radiopharmaceuticals. Main results. SADR values for 30 organs of interest were calculated via Monte Carlo simulations for 28 pediatric phantoms for the cases of five radiopharmaceuticals. The relative percentage uncertainty in the extracted dose values per organ was lower than 2.7%. An internal dosimetry prediction toolkit which can accurately predict SADRs in 30 organs for five different radiopharmaceuticals, with mean absolute percentage error on the level of 8% was developed, with specific focus on pediatric patients, by using Machine Learning regression algorithms, Single or Multiple organ training and Artificial Intelligence ensemble techniques. Significance: A large simulated dosimetry database was developed and utilized for the training of Machine Learning models. The developed predictive models provide very fast results (<2 s) with an accuracy >90% with respect to the ground truth of Monte Carlo, considering personalized anatomical characteristics and the biodistribution of each radiopharmaceutical. The proposed method is applicable to other medical dosimetry applications in different patients’ populations.

Characterisation of a monolithic ΔE-E diamond telescope detector using low energy ion microbeams

Telescope detectors have long been studied for their capability of discriminating the type of radiation detected. Silicon is the most widely used material for solid-state detectors. However, in many nuclear physics experiments and medical applications, diamond offers significant advantages due to its outstanding features, such as a near tissue equivalence, high radiation hardness and reliable operation in harsh environments. A monolithic ΔE–E diamond-based telescope was fabricated. The thicknesses of the two detection stages were 2.5 μm and 500 μm for the ΔE and E stage, respectively. The device was characterised by means of IBIC (Ion Beam Induced Charge) analysis at the Ruđer Bošković Institute ion microbeam. The detector, irradiated with different low energy ions ranging from helium to oxygen, showed good homogeneity of the response on a well-defined sensitive volume with a charge collection efficiency close to 100%. The ΔE stage showed a very good linear response on a wide range of LET values in diamond (170–3140 keV/μm). Due to its relatively low thickness, it can be successfully used as a microdosimeter. Time coincidence measurements have demonstrated the diamond telescope capability of discriminating and identifying the impinging ions. However, when the ratio between the energy deposited by the particle in the E stage and in the ΔE stage is small, the response of the E stage was observed to be affected by a cross-talk between the two stages of the device. A method to correct the E response for such effect was developed and successfully applied to the acquired data. • Development of a diamond-based ΔE-E telescope detector. • Detector characterisation by means of IBIC analysis using different low energy ions. • Thicknesses estimation by means of measurements at increasing tilt-angles. • Proof of concept for its simultaneous use as microdosimeter/particle discriminator.

Remove Liquid Radioactive Wastes Utilizing Nanofiltration, Ultrafiltration, and Microfiltration Membranes

Radioactive waste is generated from fuel cycle processes in nuclear reactors and nuclear power plants (NPPs) in electrical power production, radioisotope manufacturing in nuclear research centers, and medical, industrial, and agricultural applications. Also, natural chain-linked radioisotopes (NORM) are generated from processing and burning fossil fuels and producing oil and natural gas. Therefore, a planned and integrated radioactive waste management strategy must be adopted to protect human health and the environment from the dangers of this waste through published research on a comprehensive radioactive waste management strategy and the testing and dissemination of several treatment options. The main objective is to draw the scientific community's attention to the possibility of using pressure-driven membrane separation in treating radioactive wastewater compared to conventional methods. This short review addresses developments in the treatment and removal of radioactive effluents (LRWs) by pressure-driven membrane methods and improvements in routine treatment of dissolved radioactive ions by chemical treatment of the feed solution followed by membrane separation. Also, recent advances in treating radioactive waste use nanoparticles (NPs) incorporated in polymeric membranes.

New Developments in the Production and Research of Actinide Elements

This article briefly reviews topics related to actinide research discussed at the virtual workshop Atomic Structure of Actinides &amp; Related Topics organized by the University of Mainz, the Helmholtz Institute Mainz, and the GSI Helmholtz Centre for Heavy Ion Research, Darmstadt, Germany, and held on the 26–28 May 2021. It includes references to recent theoretical and experimental work on atomic structure and related topics, such as element production, access to nuclear properties, trace analysis, and medical applications.

Selective separation of no carrier added Sc-47 from reactor irradiated Ca using zirconium vanadate gel for nuclear medical applications

The distribution coefficient values (Kd) of 47Sc(III) ions and 47Ca(II) ions have been determined using different concentrations of HCl or HNO3 solutions on the zirconium vanadate ion exchanger (ZrV) by batch technique and the results refer to the loading of 47Sc from 0.001M HNO3 or 0.01M HCl solution onto the ZrV matrix. Different ratios of acetone solution in different HCl concentrations solutions have been investigated for the suitable elution of the adsorbed Sc-47 on ZrV . Column technique was used for separation of Sc-47 from irradiated Ca target. The elution yield of 47Sc was obtained and found to be 88 ± 4.2% using 60 % acetone-0.2M HCl mixture solution as an eluent for 47Sc with an acceptable purity of radionuclidic and radiochemical (> 99.98±0.001and 99.9±0.09 %, respectively). The Ca2+ ions level in the eluted 47Sc solution was determined and confirmed its validity for the application in labeling of pharmaceutical compounds.

Electromagnetic and Engineering Design of a High-Current 15-MeV/u Cyclotron

The capability to produce high current, low loss, and extracted external ion beams presents an enabling technology for nuclear security, isotope production, and medical applications. We report on a novel, continuous-wave cyclotron for accelerating light ions with a charge-to-mass ratio of 1/2, which is designed for 1 mA maximum and 15 MeV/u energy. This article details the conceptual electromagnetic (EM) and engineering design including the 1.1 T sector magnets and 45 MHz, 200 kV radio frequency (RF) cavities. We discuss the cyclotron beam parameters with respect to potential commercial and industrial applications. The general concept and the accelerator's layout are followed by a detailed EM design of magnets and RF cavities. Finally, practical engineering design considerations will be provided.

Physical, structural, and shielding properties of cadmium bismuth borate-based glasses

We explore a new glassy material for radiation shielding applications. Novel transparent and non-toxic Bi2O3–B2O3 glasses including different concentrations of CdO were prepared by the conventional melt quenching method. The prepared samples were characterized and analyzed by using various analytical tools (XRD, FTIR, Raman, DSC, and UV-Vis-NIR). Ab initio molecular dynamics simulations were carried out to create structural models of the materials, and these were compared to our measurements. To the best of our knowledge, this is the first study to compare the vibrations obtained experimentally with the vibrational density of states obtained from an ab initio computer model for these materials. The radiation shielding properties were measured for the photon energy range (10−3–105 MeV): both mass attenuation coefficient (μ/p) and effective atomic number (Zeff) showed a gradual increase with an increase in the CdO content. The mean-free-path, tenth value layer, half-value layer, and electron density for all prepared glasses were estimated. Promising results were achieved with the new glasses for radiation shielding purposes such as nuclear reactor and medical applications. The structural, electronic, and vibrational properties of the computer models revealed a topologically disordered, but chemically ordered network, and our vibrational computations provide direct insight into several Raman peaks observed for the materials.

Lutetium coating of nanoparticles by atomic layer deposition

Atomic layer deposition (ALD) is a versatile gas phase coating technique that allows coating of complex structured materials, as well as high-surface area materials such as nanoparticles. In this work, ALD is used to deposit a lutetium oxide layer on TiO2 nanoparticles (P25) in a fluidized bed reactor to produce particles for nuclear medical applications. Two precursors were tested: the commercially available Lu(TMHD)3 and the custom-made Lu(HMDS)3. Using Lu(TMHD)3, a lutetium loading up to 15 wt. % could be obtained, while using Lu(HMDS)3, only 0.16 wt. % Lu could be deposited due to decomposition of the precursor. Furthermore, it was observed that vibration-assisted fluidization allows for better fluidization of the nanoparticles and hence a higher degree of coating.

Status and perspectives of the neutron time-of-flight facility n_TOF at CERN

Since the start of its operation in 2001, based on an idea of Prof. Carlo Rubbia [1], the neutron time of-flight facility of CERN, n_TOF, has become one of the most forefront neutron facilities in the world for wide-energy spectrum neutron cross section measurements. Thanks to the combination of excellent neutron energy resolution and high instantaneous neutron flux available in the two experimental areas, the second of which has been constructed in 2014, n_TOF is providing a wealth of new data on neutron-induced reactions of interest for nuclear astrophysics, advanced nuclear technologies and medical applications. The unique features of the facility will continue to be exploited in the future, to perform challenging new measurements addressing the still open issues and long-standing quests in the field of neutron physics. In this document the main characteristics of the n_TOF facility and their relevance for neutron studies in the different areas of research will be outlined, addressing the possible future contribution of n_TOF in the fields of nuclear astrophysics, nuclear technologies and medical applications. In addition, the future perspectives of the facility will be described including the upgrade of the spallation target, the setup of an imaging installation and the construction of a new irradiation area.

A comparative machinability study on titanium alloy Ti-6Al-4V during dry turning by cryogenic treated and untreated condition of uncoated WC inserts

Abstract Titanium alloy is widely utilized in aerospace, nuclear power plant and medical applications due to its high hardness, corrosion resistance, specific strength and bio-compatibility. Titanium alloys are tough to machine because of its intrinsic properties such as the capability to maintain high strength at elevated temperatures, high hardness and low thermal conductivity. Moreover, titanium alloys lower thermal conductivity and high specific heat limit the effective removal of heat developed during machining through workpiece and chips. Thus it accumulates at the cutting zone. Present work deals with a comparative study on surface roughness, cutting force, and chip morphology during turning of Titanium alloy Ti-6Al-4V alloy with and without cryogenic treated uncoated tungsten carbide inserts. The cutting force and surface roughness resulting from machining with cryogenically treated inserts are comparatively lesser than machining with untreated inserts. This is due to more hardness, low thermal conductivity and high wear resistance of treated inserts.