ABSTRACT
The commercial low-pressure column chromatographic 99Mo/99mTc generator represents a reliable source of onsite, ready-to-use 99mTc for industrial applications. These generators use fission-produced 99Mo of high specific activity, posing serious production challenges and raising proliferation concerns. Therefore, many concepts are aimed at using low-specific-activity (LSA) 99Mo. Nonetheless, the main roadblock is the low sorption capacity of the used alumina (Al2O3). This study investigates the feasibility of using commercial alumina incorporated with LSA 99Mo to develop a useful 99Mo/99mTc generator for industrial radiotracer applications. First, the adsorption profiles of some commercial alumina sorbents for LSA 99Mo were tested under different experimental conditions. Then, the potential materials to develop a 99Mo/99mTc generator were selected and evaluated regarding elution yield of 99mTc and purity. Among the sorbents investigated in this study, mesoporous alumina (SA-517747) presented a unique sorption-elution profile. It demonstrated a high equilibrium and dynamic sorption capacity of 148 ± 8 and 108 ± 6 mg Mo/g. Furthermore, 99mTc was eluted with high yield and adequate chemical, radiochemical, and radionuclidic purity. Therefore, this approach provides an efficient and cost-effective way to supply onsite 99mTc for radiotracer applications independent of fission-produced 99Mo technology.
Subject(s)
Aluminum Oxide , Technetium , Aluminum Oxide/chemistry , Molybdenum/chemistry , Radioisotopes/chemistry , Radiopharmaceuticals/chemistry , Technetium/chemistryABSTRACT
Targeted Alpha Therapy (TAT) has shown very high potential for the treatment of cancers that were not responsive to other therapy options (e.g., ß- therapy and chemotherapy). The main constraint to the widespread use of TAT in clinics is the limited availability of alpha-emitting radionuclides. One of the most promising candidates for TAT is 225Ac (t1/2 = 9.92 days), which can be used directly in combination with selective biomolecules (e.g., antibodies, peptides, etc.) or be a generator source of 213Bi (t1/2 = 45.6 min), another shorter-lived TAT radionuclide. Several strategies are currently under investigation to increase the supply of 225Ac. One of the most attractive options is the irradiation of natural thorium-232 targets with high-energy protons (≥100 MeV). However, there are several challenges associated with this production method including the development of an efficient radiochemical purification method. During irradiation of natural thorium with proton energy above 100 MeV, several Ra isotopes (223,224,225Ra) are produced. 223Ra (t1/2 = 11.43 days) is used for the treatment of bone metastases and can also be used as a generator source for 211Pb. Additionally, 225Ra (t1/2 = 14.9 days) can be a valuable source of isotopically pure 225Ac. In the present work, we address the radiochemical separation aspects of isolating Ac and Ra isotopes from irradiated thorium targets.
Subject(s)
Protons , Thorium , Alpha Particles/therapeutic use , Lead , Radioisotopes/chemistry , Radioisotopes/therapeutic use , Radiopharmaceuticals/chemistry , Radiopharmaceuticals/therapeutic use , Thorium/chemistryABSTRACT
Hydroxypyridinones (HOPOs) have been used in the chelation therapy of iron and actinide metals. Their application in metal-based radiopharmaceuticals has also been increasing in recent years. This review article focuses on how multidentate HOPOs can be used in targeted radiometal-based diagnostic and therapeutic radiopharmaceuticals. The general structure of radiometal-based targeted radiopharmaceuticals, a brief description of siderophores, the basic structure and properties of bidentate HOPO, some representative HOPO multidentate chelating agents, radiopharmaceuticals based on HOPO multidentate bifunctional chelators for gallium-68, thorium-227 and zirconium-89, as well as the future prospects of HOPO multidentate bifunctional chelators in other metal-based radiopharmaceuticals are described and discussed in turn. The HOPO metal-based radiopharmaceuticals that have shown good prospects in clinical and preclinical studies are gallium-68, thorium-227 and zirconium-89 radiopharmaceuticals. We expect HOPO multidentate bifunctional chelators to be a very promising platform for building novel targeted radiometal-based diagnostic and therapeutic radiopharmaceuticals.
Subject(s)
Chelating Agents , Drug Delivery Systems , Pyridones , Radiopharmaceuticals , Chelating Agents/chemistry , Chelating Agents/therapeutic use , Gallium Radioisotopes/chemistry , Gallium Radioisotopes/therapeutic use , Humans , Pyridones/chemistry , Pyridones/therapeutic use , Radioisotopes/chemistry , Radioisotopes/therapeutic use , Radiopharmaceuticals/chemistry , Radiopharmaceuticals/therapeutic use , Thorium/chemistry , Thorium/therapeutic use , Zirconium/chemistry , Zirconium/therapeutic useABSTRACT
Theranostic applications of radiopharmaceuticals have revolutionized present era specially, dealing with cancer diseases. Increase in the uses of radionuclides in nuclear medicine has resulted in the demands of optimized new radionuclides to be produced focussing on the economy, simplicity and maximum yield. Two radionuclides of arsenic offer a well agreed theranostic systems namely 77As and 72As. Some arsenic radionuclides are capable of positron-emission, with range of hour to weeks half-lives and have potential to be used for nuclear medicine. Present work will elucidate the production of 72As on Germanium and Selenium via proton induced nuclear reactions. The experimental results obtained by several nuclear reactions were analyzed. The results of nuclear model codes namely ALICE-IPPE, EMPIRE-3.2.3 and TALYS-1.9 are compared with the experimental cross sections to generate recommended cross section data. Recommended excitation functions are used to compute the thick target yields (TTY) of 72As. Assessment of radionuclidic impurities are also studied and comparison of several radionuclidic impurities is done. To produce 72As,72Ge (p, n)72As, 73Ge (p, 2n)72As, 74Ge (p, 3n)72As and 76Se (p, x)72As reactions in different energy ranges are discussed. We have identified 72Ge (p, n)72As reaction; gives pre-eminent yield with least impurities mark it as feasible entrant to be applied in Positron Emission Tomography (PET) and theranostic applications.
Subject(s)
Arsenic/chemistry , Germanium/chemistry , Precision Medicine , Radioisotopes/chemistry , Selenium/chemistry , Computer Simulation , Positron-Emission TomographyABSTRACT
Most of South Africa's energy is derived from the combustion of coal in pulverized coal-fired power plants (CFPP). However, when compared with the rest of the world, limited information regarding the main radioactive elements (U and Th) and specific radionuclides of interest (K40, Ra226 and Th232) from South African CFPP is available in the public domain. This paper aims to quantify the U, Th and specific radionuclides found in the coal used in selected South African CFPP in comparison to world averages found in literature. The U and Th concentrations were obtained by ICP-MS. The main radionuclides, K40, Ra226 and Th238, were quantified using gamma spectrometry. The U concentration and Th concentrations for the coal used in all the power plants was above the world average of 1.9 mg/kg and 3.2 mg/kg respectively. The coals with the highest Th content originated from the Mpumalanga power plant, while the U content in the Freestate power plant samples was the highest of the three. The concentrations of the K40 were between 88.43±10.75-110.76±8.92 Bq/kg, which are in-line with world averages of 4-785 Bq/kg. Similarly, the Ra226 and Th232 values were between 21.69±2.83-52.63±4.04 Bq/kg and 19.91±1.24-22.97±1.75 Bq/kg respectively, which are also in line with the world averages of 1-206 Bq/kg and 1-170 Bq/kg respectively. Radiological hazard indices such as radium equivalent (Raeq); external hazard index (Hex) and internal hazard index (Hin), that were estimated from these average radionuclide concentrations were less than the prescribed values found in literature. This indicated that no significant health risk was posed by the coal being used from these coal fields.
Subject(s)
Coal/analysis , Power Plants , Soil Pollutants, Radioactive/isolation & purification , Coal Ash/analysis , Humans , Radiation Dosage , Radiation Monitoring , Radioisotopes/chemistry , Radioisotopes/isolation & purification , Radium/chemistry , Radium/isolation & purification , Soil Pollutants, Radioactive/chemistry , South Africa , Spectrometry, Gamma , Thorium/chemistry , Thorium/isolation & purification , Uranium/chemistry , Uranium/isolation & purificationABSTRACT
A new chemical separation has been developed to isolate uranium (U) using two UTEVA columns to minimize iron and thorium interferences from high background area soil samples containing minerals like monazites and ilmenite. The separation method was successfully verified in some certified reference materials (CRMs), for example, JSd-2, JLk-1, JB-1 and JB-3. The same method was applied for purification of U in Fukushima soil samples affected by the Fukushima dai-ichi nuclear power station (FDNPS) accident. Precise and accurate measurement of 234U/238U and 235U/238U isotope ratios in chemically separated U were carried out using a multi-collector inductively coupled plasma mass spectrometer (MC-ICP-MS). In this mass spectrometric method, an array of two Faraday cups (1011 Ω, 1012 Ω resistor) and a Daly detector were simultaneously employed. The precision of U isotope ratios in an in-house standard was evaluated by replicate measurement. Relative standard deviation (RSD) of 234U/238U and 235U/238U were found to be 0.094% (2σ) and 0.590% (2σ), respectively. This method has been validated using a standard reference material SRM 4350B, sediment sample. The replicate measurements of 234U/238U in SRM shows 0.7% (RSD). This developed method is suitable for separation of U and its isotope ratio measurement in environmental samples.
Subject(s)
Mass Spectrometry , Radioisotopes/chemistry , Soil/chemistry , Spectrum Analysis , Uranium/chemistry , Environmental Monitoring/methods , Reproducibility of Results , Soil Pollutants, RadioactiveABSTRACT
Development of a complex based on iron oxide nanoparticles (IONPs) for diagnosis and dual magnetic hyperthermia/radionuclide cancer therapy accomplishing high yields of radiolabeling and great magnetic heat induction is still a challenge. We report here the synthesis of citric acid, poly(acrylic acid) (PAA) and poly(ethylene glycol) coated IONPs and their labeling with three radionuclides, namely, technetium (99mTc), yttrium (90Y), and lutetium (177Lu), aiming at potential use in cancer diagnosis and therapy. Polyol-synthesized IONPs are a flowerlike structure with 13.5 nm spherically shaped cores and 24.8 nm diameter. PAA-coated nanoparticles (PAA@IONP) showed the best characteristics such as easy radiolabeling with very high yields (>97.5%) with all three radionuclides, and excellent in vitro stabilities with less than 10% of radionuclides detaching after 24 h. Heating ability of PAA@IONP in an alternating external magnetic field showed intrinsic loss power value of 7.3 nH m2/kg, which is one of higher reported values. Additionally, PAA@IONP itself presented no significant cytotoxicity to the CT-26 cancer cells, reaching IC50 at 60 µg/mL. However, under the external magnetic field, they show hyperthermia-mediated cells killing, which correlated with the magnetic field strength and time of exposure. Since PAA@IONP are easy to prepare, biocompatible, and with excellent magnetic heat induction, these nanoparticles radiolabeled with high-energy beta emitters 90Y and 177Lu have valuable potential as agent for dual magnetic hyperthermia/radionuclide therapy, while radiolabeled with 99mTc could be used in diagnostic imaging.
Subject(s)
Ferric Compounds/chemistry , Magnetics , Nanoparticles/chemistry , Radiopharmaceuticals/chemistry , Acrylic Resins/chemistry , Animals , Beta Particles , Cell Line, Tumor , Cell Survival/drug effects , Citric Acid/chemistry , Hyperthermia, Induced , Lutetium/chemistry , Magnetic Fields , Mice , Nanoparticles/toxicity , Neoplasms/diagnostic imaging , Particle Size , Polyethylene Glycols/chemistry , Radioisotopes/chemistry , Radiopharmaceuticals/pharmacology , Radiopharmaceuticals/therapeutic use , Technetium/chemistry , Yttrium Radioisotopes/chemistryABSTRACT
Produced water generated during unconventional oil and gas extractions contains a complex milieu of natural and anthropogenic potentially toxic chemical constituents including arsenic (As), chromium (Cr), and cadmium (Cd), naturally occurring radioactive materials (NORMs) including U and Ra, and a myriad of organic compounds. The human-ecological health risks and challenges associated with the disposal of produced water may be alleviated by understanding geochemical controls on processes responsible for the solubilization of potentially hazardous natural shale constituents to produced water. Here, we investigated, through a series of batch treatments, the leaching behavior of As, Se, Cu, Fe, Ba, Cr, Cd, and radioactive nuclides U, Ra from shale to produced water. Specifically, the effect of four major controls on element mobility was studied: (1) solution pH, (2) ionic strength of the solution, (3) oxic-anoxic conditions, and (4) an additive used in fracking fluid. The mobilization of metals and metalloids from shale was greatest in treatments containing sodium persulfate, an oxidant and a commonly used additive in fracture fluid. In the high ionic strength treatments, dissolved Ba concentrations increased 5-fold compared to low ionic strength treatments. Overall, anoxic conditions superimposed with low pH resulted in the largest increase of dissolved metals and radionuclides such as Ra. Overall, our results suggest that (1) limiting pore water acidification by injection of alkaline fluid in carbonate-low shale and (2) minimizing strong oxidizing conditions in shale formations may result in cost-effective in situ retention of produced water contaminants.
Subject(s)
Hydraulic Fracking , Radioisotopes/analysis , Trace Elements/analysis , Arsenic/analysis , Arsenic/chemistry , Barium/analysis , Barium/chemistry , Cadmium/analysis , Cadmium/chemistry , Chromium/analysis , Chromium/chemistry , Copper/analysis , Copper/chemistry , Hydrogen-Ion Concentration , Iron/analysis , Iron/chemistry , Natural Gas , Osmolar Concentration , Oxygen/analysis , Radioisotopes/chemistry , Radium/analysis , Radium/chemistry , Selenium/analysis , Selenium/chemistry , Trace Elements/chemistry , Uranium/analysis , Uranium/chemistryABSTRACT
BACKGROUND: 44Sc is becoming attractive as a PET radionuclide due to its decay characteristics. It can be produced from 44Ca present in natural calcium with 2.08% abundance. MATERIALS AND METHODS: The targets were mostly prepared from natural CaCO3 or metallic calcium in the form of pellets. After irradiation they were dissolved in 3 M hydrochloric acid and 44Sc was separated from excess of calcium by precipitation of scandium hydroxide using ammonia. Alternatively, targets were dissolved in 11 M hydrochloric acid and 44Sc was separated by extraction chromatography on UTEVA resin. As the next step, in both processes 44Sc was further purified on a cation exchange resin. Initially, the separation procedures were developed with 46Sc as a tracer. Gamma spectrometry with a high purity germanium detector was used to determine the separation efficiency. Finally, the CaCO3 pellet with 99.2% enrichment in 44Ca was activated with protons via 44Ca(p,n)44Sc nuclear reaction. RESULTS: Altogether twenty two irradiations and separations were performed. The working procedures were developed and the quality of separated 44Sc solution was confirmed by radiolabeling of DOTATATE. The chemical purity of the product was sufficient for preclinical experiments. At the end of around 1 hour proton beam irradiation of CaCO3 pellet with 99.2% enrichment in 44Ca the obtained radioactivity of 44Sc was more than 4.8 GBq. CONCLUSION: 44Sc can be produced inexpensively with adequate yields and radionuclidic purity via 44Ca(p,n)44Sc nuclear reaction in small cyclotrons. The recovery yield in both investigated separation methods was comparable and amounted above 90%. The obtained 44Sc was pure in terms of radionuclide and chemical purity, as shown by the results of peptide radiolabeling.
Subject(s)
Actinoid Series Elements/chemistry , Chemical Precipitation , Hydroxides/chemistry , Radiochemistry/methods , Radioisotopes/chemistry , Radioisotopes/isolation & purification , Scandium/chemistry , Scandium/isolation & purification , Uranium/chemistry , Calcium Carbonate/chemistry , Cyclotrons , Isotope Labeling , Radiochemistry/instrumentationABSTRACT
The environmental pollutions by organic pollutants and radionuclides have aroused great concern. Developing highly efficient elimination methods becomes an imperious demand. In this study, a nanocomposite of K2Ti6O13 (KTO) nanobelts hybridized graphene oxide (GO) nanosheets (GO/KTO) was used to photodegrade RhB (dye) and photoreduce U(VI) (radionuclide), which was synthesized by a facile hydrothermal method. The adsorption capacity and the slope (k) of the curve -ln(C/C) versus time in photodegradation of RhB by GO/KTO were higher than that by GO and KTO. In the presence of different free radical scavengers, superoxide radical (·O2-) was found to play the most significant role in the reaction. The XPS experiment indicates U(VI) was successfully photoreduced to less toxic U(IV). The pH dependent photocatalytic experiments on RhB and U(VI) both showed the best performance at neutral pH value (from pH 6 to pH 8). To investigate the reason for the enhanced photocatalysis of GO/KTO, the morphology/microstructure, optical and photo-electrochemical properties were examined. The enhanced abilities of separation of photo electrons and holes and the adsorption of GO/KTO were ascribed to the structure of KTO nanobelts laying on the surface of GO nanosheets, which may maximize the contacting area between KTO and GO, and thus greatly reduce the surface related oxygen defects to enhance the electron interface transfer between KTO and GO and decrease the recombination efficiency of electrons and holes. These results showed the GO/KTO has great application potential in environmental treatment of organic pollutants and high valent heavy/radionuclide ions at neutral condition.
Subject(s)
Graphite/chemistry , Photolysis , Radioisotopes/chemistry , Rhodamines/metabolism , Titanium/chemistry , Uranium/chemistry , Adsorption , Nanocomposites , Superoxides/chemistryABSTRACT
BACKGROUND: With the advances in radiopharmaceutical research, the development of image-guided therapy has become a major interest. While the development of theranostic nanotherapeutics is frequently associated with cancer chemotherapy, phototherapy and radiotherapy, there is little information available on the in vivo monitoring of gene delivery systems and the application of image-guided approach in gene therapy. The goal of this work was to determine the in vivo behavior of DNA delivery nanosystems - based on cationic gemini surfactants - designed for image-guided gene therapy. We tested the feasibility of monitoring tumor accumulation of gene delivery nanoparticles by positron emission tomography. METHODS: To be able to conjugate radiotracers to the nanoparticles, a deferoxamine-modified gemini surfactant was synthesized, DNA-containing lipoplex nanoparticles were formulated, and radiolabeled with Zirconium-89 (89Zr). The pharmacokinetics and biodistribution of 89Zr labeled surfactant and 89Zr labeled nanoparticles were monitored in mice by microPET/CT imaging and ex vivo gamma counting. RESULTS: Modification of the nanoparticles with deferoxamine did not alter their physicochemical properties. The radiolabeled nanoparticles (labeling efficiency of 95±3%) were stable in PBS and serum. The biological half-life of the 89Zr labeled nanoparticles was significantly higher compared to 89Zr labeled surfactant. As expected, the nanoparticles had significantly higher liver accumulation than the radiolabeled surfactant alone and lower kidney accumulation. Tumor uptake was detected at 2 hours post injection and decreased throughout the 3-day monitoring. CONCLUSION: We propose that radiolabeling DNA delivery lipoplex nanosystems is a promising approach for the design and optimization of image-guided nanomedicines, especially in the context of cancer gene therapy.
Subject(s)
Gene Transfer Techniques , Imaging, Three-Dimensional , Lipids/chemistry , Nanoparticles/chemistry , Radioisotopes/chemistry , Zirconium/chemistry , Animals , Cell Survival , Deferoxamine/chemistry , Gene Expression Regulation , Genetic Therapy , Mice, Nude , Nanoparticles/ultrastructure , Neoplasms/metabolism , Neoplasms/pathology , Positron-Emission Tomography , Radioisotopes/pharmacokinetics , Radiopharmaceuticals/pharmacokinetics , Surface-Active Agents/chemistry , Tissue Distribution , Zirconium/pharmacokineticsABSTRACT
The interaction between radionuclides and nanomaterials could generate Cerenkov radiation (CR) for CR-induced photodynamic therapy (PDT) without requirement of external light excitation. However, the relatively weak CR interaction leaves clinicians uncertain about the benefits of this new type of PDT. Therefore, a novel strategy to amplify the therapeutic effect of CR-induced PDT is imminently required to overcome the disadvantages of traditional nanoparticulate PDT such as tissue penetration limitation, external light dependence, and low tumor accumulation of photosensitizers. Herein, magnetic nanoparticles (MNPs) with 89Zr radiolabeling and porphyrin molecules (TCPP) surface modification (i.e., 89Zr-MNP/TCPP) were synthesized for CR-induced PDT with magnetic targeting tumor delivery. As a novel strategy to break the depth and light dependence of traditional PDT, these 89Zr-MNP/TCPP exhibited high tumor accumulation under the presence of an external magnetic field, contributing to excellent tumor photodynamic therapeutic effect together with fluorescence, Cerenkov luminescence (CL), and Cerenkov resonance energy transfer (CRET) multimodal imaging to monitor the therapeutic process. The present study provides a major step forward in photodynamic therapy by developing an advanced phototherapy tool of magnetism-enhanced CR-induced PDT for effective targeting and treatment of tumors.
Subject(s)
Magnetite Nanoparticles/chemistry , Photochemotherapy , Animals , Cell Survival/drug effects , Female , Fluorescence Resonance Energy Transfer , Humans , Mammary Neoplasms, Experimental/diagnostic imaging , Mammary Neoplasms, Experimental/pathology , Mice , Mice, Inbred BALB C , Porphyrins/chemistry , Porphyrins/pharmacology , Positron-Emission Tomography , Radioisotopes/chemistry , Radioisotopes/pharmacology , Tumor Cells, Cultured , Zirconium/chemistry , Zirconium/pharmacologyABSTRACT
The phosphogypsum (PG) stacks located at Huelva (SW Spain) store about 100â¯Mt of PG, and covers a surface of 1000â¯ha. It has been very well established in many studies that this waste contains significant U-series radionuclides concentrations, with average activity concentrations rounding the 650, 600, 400 and 100 Bq kg-1 for 226Ra, 210Po, 230Th and 238U, respectively. However, the radionuclide transfer from this repository into the environment by the aquatic pathway will depend on the mobility of each radionuclide. The mobility of the natural radionuclides (U-isotopes, Th-isotopes, 226Ra, and 210Po) contained in the PG piles were evaluated by using the optimized BCR sequential extraction procedure (BCR "Community Bureau of Reference"). The radionuclides were measured in the liquid fractions by alpha-particle spectrometry with semiconductor PIPS detectors. In addition, to validate the obtained results, waters from different locations of the PG piles (pore-water, perimeter channel and edge outflow leachates) were taken and the alpha emitter radionuclides determined. Uranium presents the highest mobility, being its total mobile fraction in the PG around 70%, while 210Po and 226Ra present an intermediate mobility of (around 50% and 30%, respectively). And finally, the Th-isotopes have very low mobility (mobile fractionâ¯<â¯5%), being fixed to the residual fraction. It is noteworthy that this behaviour has been also found in the water samples taken from the stacks, demonstrating that this sequential leaching operational methodology is a useful tool for assessing the release capacity of radionuclides by inorganic wastes.
Subject(s)
Calcium Sulfate/chemistry , Phosphorus/chemistry , Radioisotopes/chemistry , Soil Pollutants, Radioactive/chemistry , Radioisotopes/analysisABSTRACT
Pretargeted nuclear imaging and radiotherapy have recently attracted increasing attention for diagnosis and treatment of cancer with nanomedicines. This is because it conceptually offers better imaging contrast and therapeutic efficiency while reducing the dose to radiosensitive tissues compared to conventional strategies. In conventional imaging and radiotherapy, a directly radiolabeled nano-sized vector is administered and allowed to accumulate in the tumor, typically on a timescale of several days. In contrast, pretargeting is based on a two-step approach. First, a tumor-accumulating vector carrying a tag is administered followed by injection of a fast clearing radiolabeled agent that rapidly recognizes the tag of the tumor-bound vector in vivo. Therefore, pretargeting circumvents the use of long-lived radionuclides that is a necessity for sufficient tumor accumulation and target-to-background ratios using conventional approaches. In this review, we give an overview of recent advances in pretargeted imaging strategies. We will critically reflect on the advantages and disadvantages of current state-of-the-art conventional imaging approaches and compare them to pretargeted strategies. We will discuss the pretargeted imaging concept and the involved chemistry. Finally, we will discuss the steps forward in respect to clinical translation, and how pretargeted strategies could be applied to improve state-of-the-art radiotherapeutic approaches.
Subject(s)
Nanomedicine/methods , Theranostic Nanomedicine/methods , Radioisotopes/chemistryABSTRACT
High sensitivity imaging tools could provide a more holistic view of target antigen expression to improve the identification of patients who might benefit from cancer immunotherapy. We developed for immunoPET a novel recombinant human IgG1 (termed C4) that potently binds an extracellular epitope on human and mouse PD-L1 and radiolabeled the antibody with zirconium-89. Small animal PET/CT studies showed that 89Zr-C4 detected antigen levels on a patient derived xenograft (PDX) established from a non-small-cell lung cancer (NSCLC) patient before an 8-month response to anti-PD-1 and anti-CTLA4 therapy. Importantly, the concentration of antigen is beneath the detection limit of previously developed anti-PD-L1 radiotracers, including radiolabeled atezolizumab. We also show that 89Zr-C4 can specifically detect antigen in human NSCLC and prostate cancer models endogenously expressing a broad range of PD-L1. 89Zr-C4 detects mouse PD-L1 expression changes in immunocompetent mice, suggesting that endogenous PD-1/2 will not confound human imaging. Lastly, we found that 89Zr-C4 could detect acute changes in tumor expression of PD-L1 due to standard of care chemotherapies. In summary, we present evidence that low levels of PD-L1 in clinically relevant cancer models can be imaged with immunoPET using a novel recombinant human antibody.
Subject(s)
B7-H1 Antigen/analysis , Carcinoma, Non-Small-Cell Lung/diagnostic imaging , Immunoconjugates/chemistry , Immunoglobulin G/chemistry , Lung Neoplasms/diagnostic imaging , Positron Emission Tomography Computed Tomography/methods , Radioisotopes/chemistry , Zirconium/chemistry , Animals , Cell Line, Tumor , HEK293 Cells , Humans , Lung/diagnostic imaging , Male , Mice , Mice, Inbred C57BL , Recombinant Proteins/chemistryABSTRACT
Black sand samples collected from Baltim beaches (Kafr El-Sheikh governorate) in Egypt on the Mediterranean Sea shore were analyzed radiometrically and evaluated using a nondestructive gamma ray spectroscopic techniques. The natural radionuclides of 226Ra, 232Th and 40K in the black sand samples were identified and quantified. It is found that the activity concentrations for 226Ra, 232Th and 40K in different eleven sites (S1S11) were found within the ranges of 28-322, 91-308 and 81-339 Bq/kg, respectively. Moreover, different radiological hazardous parameters (absorbed dose rate, annual effective dose equivalent, radium activity, annual gonadal dose equivalent and excess lifetime cancer risk) were calculated. The results show that these values are greater than the permissible values due to increasing the activity concentrations of the primordial radionuclides 226Ra, 232Th and 40K. The dose rate for radiation emitted at 1â¯m from the surface of land was measured directly and the results shown that all sites emit radiation doses more than the international permissible value (57â¯nGy/h) especially at three sites which around 340â¯nGy/h. These values are important to establish baseline levels of this environmental radioactivity to detect any upcoming change for the local population and resorts people. The relatively high dose rate will be considered as a spa for the physical therapy such as treatment of some skin diseases and rheumatoid.
Subject(s)
Potassium Radioisotopes/chemistry , Radiation Monitoring/methods , Radioisotopes/chemistry , Radium/chemistry , Soil Pollutants, Radioactive/analysis , Thorium/chemistry , Environmental Monitoring/methods , Gamma Rays , Mediterranean Sea , Radiation Dosage , RadioactivityABSTRACT
PURPOSE: Increased angiogenesis is a marker of aggressiveness in many cancers. Targeted radionuclide therapy of these cancers with angiogenesis-targeting agents may curtail this increased blood vessel formation and slow the growth of tumors, both primary and metastatic. CD105, or endoglin, has a primary role in angiogenesis in a number of cancers, making this a widely applicable target for targeted radioimmunotherapy. METHODS: The anti-CD105 antibody, TRC105 (TRACON Pharmaceuticals), was conjugated with DTPA for radiolabeling with 177Lu (t 1/2 6.65 days). Balb/c mice were implanted with 4T1 mammary carcinoma cells, and five study groups were used: 177Lu only, TRC105 only, 177Lu-DTPA-IgG (a nonspecific antibody), 177Lu-DTPA-TRC105 low-dose, and 177Lu-DTPA-TRC105 high-dose. Toxicity of the agent was monitored by body weight measurements and analysis of blood markers. Biodistribution studies of 177Lu-DTPA-TRC105 were also performed at 1 and 7 days after injection. Ex vivo histology studies of various tissues were conducted at 1, 7, and 30 days after injection of high-dose 177Lu-DTPA-TRC105. RESULTS: Biodistribution studies indicated steady uptake of 177Lu-DTPA-TRC105 in 4T1 tumors between 1 and 7 days after injection (14.3 ± 2.3%ID/g and 11.6 ± 6.1%ID/g, respectively; n = 3) and gradual clearance from other organs. Significant inhibition of tumor growth was observed in the high-dose group, with a corresponding significant increase in survival (p < 0.001, all groups). In most study groups (all except the nonspecific IgG group), the body weights of the mice did not decrease by more than 10%, indicating the safety of the injected agents. Serum alanine transaminase levels remained nearly constant indicating no damage to the liver (a primary clearance organ of the agent), and this was confirmed by ex vivo histological analyses. CONCLUSION: 177Lu-DTPA-TRC105, when administered at a sufficient dose, is able to curtail tumor growth and provide a significant survival benefit without off-target toxicity. Thus, this targeted agent could be used in combination with other treatment options to slow tumor growth allowing the other agents to be more effective.
Subject(s)
Antibodies, Monoclonal/therapeutic use , Lutetium/chemistry , Neoplasms, Experimental/radiotherapy , Neovascularization, Pathologic/radiotherapy , Radioimmunotherapy/methods , Radioisotopes/chemistry , Radiopharmaceuticals/therapeutic use , Animals , Antibodies, Monoclonal/chemistry , Antibodies, Monoclonal/immunology , Cell Line, Tumor , Endoglin/immunology , Female , Mice , Mice, Inbred BALB C , Neoplasms, Experimental/pathology , Pentetic Acid/chemistry , Radiopharmaceuticals/adverse effects , Radiopharmaceuticals/chemical synthesis , Radiopharmaceuticals/pharmacokinetics , Tissue DistributionABSTRACT
Advanced techniques for detecting kinase inhibitors are in demand due to limitations of traditional approaches. Here, we used a fluorescence resonance energy transfer (FRET)-based kinase assay, a sensitive fluorescence turn-on biosensing platform, to identify a Polo-like kinase 1 (PLK1) inhibitor. The assay was developed with the Z'-Lyte™ FRET-peptide and PLK1 kinase purified from a baculovirus expression system. Using PLK1 inhibitors, sensitivity and efficiency of this FRET-based PLK1 kinase assay were compared to those of radioisotope-based and immunoblot-based assays. Although the inhibitory activity of BI 2536 against PLK1 kinase in each assay was almost the same, the FRET-based PLK1 kinase assay was much easier, faster, safer, and more convenient than a radioisotope-based assay or an immunoblot-based traditional kinase assay. From our findings, we suggest that a FRET-based PLK1 kinase assay is an advanced tool which overcomes the limitations of previous traditional kinase assays to detect kinase inhibitors for the development of anticancer drugs.
Subject(s)
Antineoplastic Agents/chemistry , Cell Cycle Proteins/antagonists & inhibitors , Cell Cycle Proteins/metabolism , Drug Evaluation, Preclinical/methods , Fluorescence Resonance Energy Transfer , Protein Serine-Threonine Kinases/antagonists & inhibitors , Protein Serine-Threonine Kinases/metabolism , Proto-Oncogene Proteins/antagonists & inhibitors , Proto-Oncogene Proteins/metabolism , Animals , Benzimidazoles/chemistry , Biological Assay , Biomarkers, Tumor/metabolism , Fluorescent Dyes/chemistry , Genistein/chemistry , Glutathione Transferase/metabolism , Humans , Insecta , Peptides/chemistry , Pteridines/chemistry , Radioisotopes/chemistry , Thiophenes/chemistry , Tumor Protein, Translationally-Controlled 1 , Polo-Like Kinase 1ABSTRACT
Radioimmunotherapy (RIT) delivers radioisotopes to antigen-expressing cells via monoantibodies for the imaging of lesions or medical therapy. The chelates are typically conjugated to the antibody through cysteine or lysine residues, resulting in heterogeneous chelate-to-antibody ratios and various conjugation sites. To overcome this heterogeneity, we have developed an approach for site-specific radiolabeling of antibodies by combination of genetic code expansion and click chemistry. As a proof-of-concept study, model systems including anti-CD20 antibody rituximab, positron-emitting isotope 64Cu, and a newly synthesized bifunctional linker (4-dibenzocyclooctynol-1,4,7,10-tetraazacyclotetradecane-1,4,7,10-tetraacetic acid, DIBO-DOTA) were used. The approach consists of three steps: (1) site-specific incorporation of an azido group-bearing amino acid (NEAK) via the genetic code expansion technique at the defined sites of the antibody as a "chemical handle"; (2) site-specific and quantitative conjugation of bifunctional linkers with the antibodies under a mild condition; and (3) radiolabeling of the chelate-modified antibodies with the appropriate isotope. We used heavy-chain A122NEAK rituximab as proof-of-concept and obtained a homogeneous radioconjugate with precisely two chelates per antibody, incorporated only at the chosen sites. The conjugation did not alter the binding and pharmacokinetics of the rituximab, as indicated by in vitro assays and in vivo PET imaging. We believe our research is a good supplement to the genetic code expansion technique for the development of novel radioimmunoconjugates.
Subject(s)
Copper Radioisotopes/chemistry , Immunoconjugates/chemistry , Positron-Emission Tomography/methods , Radioimmunotherapy/methods , Rituximab/chemistry , Animals , Benzoxazines/chemistry , Chelating Agents/chemistry , Chemistry Techniques, Synthetic , Drug Stability , Heterocyclic Compounds, 1-Ring/chemistry , Humans , Isotope Labeling/methods , Lutetium/chemistry , Mice, SCID , Radioisotopes/chemistry , Rituximab/genetics , Rituximab/pharmacokineticsABSTRACT
Radioisotope therapy (RIT), in which radioactive agents are administered or implanted into the body to irradiate tumors from the inside, is a clinically adopted cancer treatment method but still needs improvement to enhance its performances. Herein, it is found that polyethylene glycol (PEG) modified tungsten disulfide (WS2 ) nanoflakes can be easily labeled by (188) Re, a widely used radioisotope for RIT, upon simple mixing. Like other high-Z elements acting as radiosensitizers, tungsten in the obtained (188) Re-WS2 -PEG would be able to absorb ionization radiation generated from (188) Re, enabling ''self-sensitization'' to enhance the efficacy of RIT as demonstrated in carefully designed in vitro experiments of this study. In the meanwhile, the strong NIR absorbance of WS2 -PEG could be utilized for NIR light-induced photothermal therapy (PTT), which if applied on tumors would be able to greatly relieve their hypoxia state and help to overcome hypoxia-associated radioresistance of tumors. Therefore, with (188) Re-WS2 -PEG as a multifunctional agent, which shows efficient passive tumor homing after intravenous injection, in vivo self-sensitized, NIR-enhanced RIT cancer treatment is realized, achieving excellent tumor killing efficacy in a mouse tumor model. This work presents a new concept of applying nanotechnology in RIT, by delivering radioisotopes into tumors, self-sensitizing the irradiation-induced cell damage, and modulating the tumor hypoxia state to further enhance the therapeutic outcomes.