Gamma-emitting Radionuclides Research Articles

Radiation protection and natural building materials in cultural heritage

IntroductionBuildings that constitute cultural heritage and that are the identity of a defined geographical area are increasingly being restored to offer the community historical places to enjoy. Often the restoration preserves the original structure and building materials, which are usually natural stones. In this study, a radioprotection protocol dedicated to this kind of built environment was proposed and validated.MethodsAfter identifying the two predominant types of building material stones (Rosso ammonitico and Pietra Serena), radiometric measurements for natural gamma-emitting radionuclides (Ra-226, Th-232, and K-40) and measurements of the emanation coefficient and calculation of the exhalation rate of radon gas were carried out.ResultsThe two types of stone have a content of natural radionuclides that do not exceed the levels recommended by the regulations. The difference between the two types of stone is of an order of magnitude indicating that the red ammonite has a greater radiological impact than the pietra serena.DiscussionThe results, in addition to ensuring the radioprotection of the population, highlighted the need to increase the number of this kind of investigations to implement scientific knowledge and serve the stakeholders involved.

Radiological characterization of materials used in the Italian heritage buildings

Building materials (BMs) can cause significant gamma dose indoors due to their natural radionuclide content. In 2013, the European Directive 59/2013/EURATOM introduced, in annex XIII, a list of types of BMs of interest for the content of gamma-emitting radionuclides among which materials or additives of natural igneous origin, such as granitoids, tuff and lava, are included. These materials have been largely employed for decorative and structural purposes in the course of centuries in the Italian heritage buildings. Aim of this study is to assess the contribute of BMs in terms of alpha exposure. Six samples of different materials, characterized in a previous study by the authors in terms of radiological content by means of a gamma spectrometry, have been analyzed in order to determine the specific exhalation rate of 222Rn, the radon emanation coefficient and excess in indoor radon concentration. Results confirm that BMs of natural igneous origin can play an important role in terms of alpha radiation dose and internal exposure due to the inhalation of the alpha particles emitted.

Long-lived Gamma-Emitting Radionuclides in Commonly Consumed Imported Coffee Brands in Lagos and the Total Committed Effective Dose using a High Purity Germanium Detector

Long-lived Gamma-Emitting Radionuclides in Commonly Consumed Imported Coffee Brands in Lagos and the Total Committed Effective Dose using a High Purity Germanium Detector

Radiolabeled Probes from Derivatives of Natural Compounds Used in Nuclear Medicine.

Natural compounds are important precursors for the synthesis of new drugs. The development of novel molecules that are useful for various diseases is the main goal of researchers, especially for the diagnosis and treatment of many diseases. Some pathologies need to be treated with radiopharmaceuticals, and, for this reason, radiopharmaceuticals that use the radiolabeling of natural derivates molecules are arousing more and more interest. Radiopharmaceuticals can be used for both diagnostic and therapeutic purposes depending on the radionuclide. β+- and gamma-emitting radionuclides are used for diagnostic use for PET or SPECT imaging techniques, while α- and β--emitting radionuclides are used for in metabolic radiotherapy. Based on these assumptions, the purpose of this review is to highlight the studies carried out in the last ten years, to search for potentially useful radiopharmaceuticals for nuclear medicine that use molecules of natural origin as lead structures. In this context, the main radiolabeled compounds containing natural products as scaffolds are analyzed, in particular curcumin, stilbene, chalcone, and benzofuran. Studies on structural and chemical modifications are emphasized in order to obtain a collection of potential radiopharmaceuticals that exploit the biological properties of molecules of natural origin. The radionuclides used to label these compounds are 68Ga, 44Sc, 18F, 64Cu, 99mTc, and 125I for diagnostic imaging.

A baseline monitoring of radiological sediment quality and associated risk assessment in coastal ecosystems of the Republic of Congo.

This study presents the first data on levels of natural radioactive elements in sediments from coastal ecosystems of the Republic of Congo. Sediment samples from five coastal sites were collected and analyzed by high-resolution gamma spectrometry for determination of activities of long-lived gamma-emitting radionuclides (234Th, 238U, 226Ra, 210Pb, 228Th, 228Ra, and 40K). The specific activities were of the same order of magnitude as those measured in sediments of most countries neighboring the Republic of Congo. However, variations in activities were observed from one site to another and also from one sampling point to another within the same site without exceeding the global average reference values. It can be assumed, therefore, that no significant anthropogenic impact is perceptible in the study area. The most commonly used radiological hazard parameters, based mainly on 238U, 232Th, and 40K activities, were assessed and the ERICA tool was applied to quantify the radiation exposure burden to human and biota resulting from radionuclides in sediments. Besides being useful for future monitoring efforts, the data produced in this work could be important for the worldwide database on radioactivity in the oceans and seas (MARIS) since no data are available in the Congolese marine environment.

Radioactive glassy inclusions in the soil sampled at the “Taiga” peaceful underground nuclear explosions site (the Perm region, Russia)

Activities of gamma-emitting radionuclides were measured in glassy inclusions (particles) found in soil samples from the “Taiga” peaceful nuclear explosions site (the Perm region, Russia). The measurements were performed using a stationary semiconductor gamma spectrometer. Activity concentrations were determined for the following technogenic radionuclides: 60Co, 94Nb, 137Cs, 152Eu, 154Eu, 155Eu, and 241Am. The activity concentrations of 241Am in the glassy inclusions were one to two orders of magnitude higher compared to the level of minimum significant activity concentration (1 Bq/g for 241Am) established by the Russian Radiation Safety Standards “NRB-99/2009”. Earlier, exceeding this level for the 241Am activity concentration in the native (unfractionated) soil samples from the “Taiga” site was reported by other researchers. In accordance with current Russian legislative and regulatory provisions regarding use of nuclear charges for peaceful purposes, the soil and radioactive glassy inclusions found in the soil correspond to the category of special radioactive waste. Considering the long half-life of 241Am (432 years), radiologically significant contamination by this radionuclide will persist at the “Taiga” site for the foreseeable future.

Radiocontamination level of mussels (M. Galloprovincialis) collected in italy from apulian coasts and assessed dose to population

Due to their particular metabolism, bio-filtering mollusks accumulate elements essential for their sustenance, but even radioactive isotopes of natural elements, such as Uranium and Polonium. Many of these cannot be directly determined by gamma spectrometry, since chemical separation from the matrix is needed before determining activity concentration by means of different spectrometric techniques and the dose to the consumer. In this paper, the authors describe the methods and present the results of alpha, beta and gamma radiometric measurements on filtering mollusks samples (M. Galloprovincialis) collected along the Apulian coast (Italy) during 2021. The analyses were carried in order to give an overall picture of the radio-contamination on the Italian side of the Adriatic Sea. The artificial gamma-emitting radionuclides (e.g. I-131, Co-60, Cs-134) were not detected in all samples. Strontium-90 alone was often found to be present at extremely low concentration, in the range 0.01 – 0.57 Bq kg−1. With reference to natural radionuclides (i.e., U-234, U-235, U-238 and Lead-210) the activity concentrations were limited to a few Bq kg−1. Po-210 represents a particular case, since it results more accumulated than its parent nuclide Lead-210, indicating that polonium is selectively accumulated by mussels. Using ICRP-Dose software, the annual dose to population was assessed. The results demonstrated that the annual limit of one mSv (Italian law) could be exceeded only if the annual consumption exceeds 200 kg per capita of fresh mussels. In conclusion the analysis showed that Polonium-210 and Lead-210 were selectively accumulated by mussels, with particular reference to Polonium. However, the activities are in any case such as not to cause concern for consumers.

The European intercomparison of in-vivo monitoring laboratories: the EIVIC-2020 project

The EIVIC project was launched in 2020, and the main goal was the organisation of a European intercomparison of in-vivo monitoring laboratories dealing with direct measurements of gamma-emitting radionuclides incorporated into the body of exposed workers. This project was organised jointly by members of EURADOS Working Group 7 on internal dosimetry (WG7), the Federal Office for Radiation Protection (BfS, Germany) and the Radioprotection and Nuclear Safety Institute (IRSN, France). The objective was to assess the implementation of individual-monitoring requirements in EU Member States on the basis of in-vivo measurements and to gain insight into the performance of in-vivo measurements using whole-body counters. In this context, a total of 41 in-vivo monitoring laboratories from 21 countries, together with JRC (EC) and IAEA participated. The results were submitted in terms of activity (Bq) of the radionuclides identified inside phantoms that were circulated to all participants. The measured data were compared with reference activity values to evaluate the corresponding bias according to the standards ISO 28218 and ISO 13528. In general, the results of the different exercises are good, and most facilities are in conformity with the criteria for the bias and z-scores in the ISO standards. Furthermore, information about technical and organisational characteristics of the participating laboratories was collected to test if they had a significant influence on the reported results.

РАДИОЭКОЛОГИЧЕСКАЯ ОБСТАНОВКА В РАЙОНЕ ПЛОЩАДКИ УРАНОВОГО НАСЛЕДИЯ – ШАХТА «СТЕПНАЯ» (КАЛМЫКИЯ)

Purpose: To study the radio-ecological situation on the “uranium legacy” site of the former Stepnaya mine in the Republic of Kalmykia. Material and methods: To measure the ambient dose equivalent rate (ADER), the pedestrian gamma survey method was used using a portable spectrometric complex MKC-01A Multirad-M and dosimeter-radiometer MKC-AT6101c. The activity of gamma-emitting radionuclides in soil samples was measured using a stationary gamma spectrometer from CANBERRA. The activities of 210Po and 210Pb were measured using a radiometric installation UMF-2000 following their radiochemical separation from samples. Short-term measurements of activity concentration (AC) and equivalent equilibrium activity concentration (EEAC) of radon were carried out with an aerosol alpha radiometer for radon and thoron RAA-20P2 Poisk. Doses of radiation exposure to biological objects were estimated using dose coefficients provided by ICRP Publication 136 taking into account recommendations R52.18.820-2015. Results: Gamma ADER values at the mine site vary over the range from 0.1 to 0.36 µSv/h, and on 80 % of the area these values do not exceed the background value of 0.14 µSv/h. Along the road from the mine to Narta village the ADER values do not exceed background values with exception of the area around the dam, where in a local part of this area of about 300 m2 these values reach 0.49 µSv/h. The specific activities of natural radionuclides in the soil are below the criteria for classification as solid radioactive waste (SRW). Under the certain weather conditions, radon EEAC inside the buildings on the site reaches 13 kBq/m3, and on the territory 1-1.5 kBq/m3. Ecological risk for the terrestrial biological objects under consideration (grass, soil worm, snake and mouse-like rodents) does not exceed 0.025. Conclusions: The radiation situation at the Stepnaya mine site meets the requirements of SP LKP-91, which were in force until 2020. However, in order to transfer the facility to a local government body, reclamation work should be carried out in accordance with the Federal Law “On the Transfer of Lands or Land Plots from One Category to Another” dated December 21, 2004 No. 172-FZ and GOST R 59057— 2020 «Environmental Protection. Lands. General Requirements for Reclamation of Affected Lands». Doses of exposure to biological objects do not impact significantly on morbidity, reproduction and life expectancy of terrestrial biological objects.

Assessing soil erosion in a semiarid ecosystem in Central Argentina using 137Cs and 7Be measurements

ABSTRACT Argentina is a Latin American country which encounters soil degradation problems. The most productive regions have implemented conservative land practices (no-till). However, agricultural frontier has been displaced to marginal lands with arid and semiarid climates, with the consequent disappearance in many areas of native forest and land degradation. In this work, the fallout of gamma-emitting radionuclides, 137Cs and 7Be, was jointly used to assess changes in soil erosion in a recently converted semiarid ecosystem into agricultural land. 137Cs was utilized to estimate the erosion over the past 60 years, whereas 7Be was employed to estimate the erosion after the conversion of the area to cultivated land and soil tillage. For 137Cs the Proportional Model (PM), the Mass Balance Model II (MBMII) and the MODERN model were used, for 7Be the Profile Distribution Model (PDM) and the MODERN model were used. 137Cs indicates mean erosional rates of 8.2, 10.5 and 6.5 Mg ha−1 a−1, using MBMII, PM and MODERN, respectively, and that a soil layer between 0.5 and 0.8 mm was annually lost by erosion. By applying a 7Be tracer, we measured erosion rates of 2.4 and 3.3 Mg ha−1 (with PDM and Modern, respectively), indicating the loss of the upper 0.2 mm of soil. This erosion can be attributed to a few heavy rainfalls that occurred within the past 90 days. The results suggest that current land management practices have led to an increase in soil erosion. This could be attributed to the fact that the soil remains bare after crop harvest, which may compromise its conservation and future productivity.

Effective methods for monitoring internal contamination among workers handling radioactive materials in various fields

This study aimed to develop effective methods for monitoring internal contamination among workers handling radioactive materials in various fields. A total of 160 workers from nuclear power plants, medical institutions, military units, and educational/research institutions were included in the study. The monitoring methods included urinalysis and whole-body counting (WBC) using a mobile radio bioassay laboratory (MRL). Gamma-emitting radionuclides were monitored using the MRL WBC system, and a separate pretreatment procedure was used for tritium measurement in urine samples. Gross beta-screening was performed using a liquid scintillation counting system. The results were evaluated on the basis of the established screening criteria and compared with the dose limits. Additionally, tritium concentrations in the bodies of workers in the vicinity of a heavy-water reactor was analysed to assess the association between tritium concentration and occupation. The results showed a wide distribution of tritium concentrations. Workers involved in fuel and maintenance tasks demonstrated the maximum exposure. Workers in medical facilities showed low levels of internal contamination, which was primarily related to tasks involving radioactive isotopes. Military personnel involved in equipment repair showed significant tritium contamination due to damage during repairs. Workers in educational and research institutions in general had low levels of internal contamination.

Радиоэкологическая обстановка в районе вводимого в эксплуатацию рудника № 6 пао «Приаргунское горно-химическое производственное объединение»

Purpose: Study of the radioecological situation around mine No. 6 of PJSC ‘Priargunsky Industrial Mining and Chemical Association’ named after E.P. Slavskiy" before commissioning. Material and Methods: During the radiation survey, to measure the ambient dose equivalent rate, the pedestrian gamma survey method was used using the portable spectrometric complex MKS-01A ‘Multirad-M’ (Russia) and the dosimeter-radiometer MKS-AT6101s (Belarus). To study the specific activity of radionuclides in the soil, samples were taken in accordance with GOST 17.4.3.01-2017. The activity of gamma-emitting radionuclides was measured on a stationary gamma spectrometer manufactured by Canberra (USA). The activity of 210Po and 210Pb was measured on the radiometric system UMF-2000 (Russia) after their radiochemical extraction from samples. Dose assessment of exposure to biological objects was made using dose coefficients established in ICRP Publication 136, considering recommendations R52.18.820-2015. Results: The results of the study showed that the ambient dose equivalent rate of gamma radiation varied in a wide range from 0.1 to 4.9 µSv/h. The average value in the background areas is 0.14±0.02 µSv/h. The specific activity of natural radionuclides outside the rock dumps, except for 40K, in some areas exceeds the background values up to 10 times. The ecological risk for the considered terrestrial biological objects (grass, shrub, soil worm and mouse-like rodents) does not exceed 10‒2. Conclusion: There are areas on the territory with traces of anthropogenic activity, which led to man-made radiation contamination. The highest levels of ambient dose equivalent of gamma radiation occur near rock dumps. The rest of the territory has local areas with radioactive contamination. Doses of exposure to biological objects don’t have a significant effect on the incidence, reproduction, and life expectancy of terrestrial biological objects.

Gamma-emitting radionuclides in therapeutic muds of the Euganean Thermal District (Padua, Italy)

Mud therapy is a therapeutic tool which uses natural materials available in the environment for healing purposes (clays and thermal water). The use of natural remedies increases the compliance to the cure, and their success is increasing in the last decades, all over the world. As natural matters, also muds have a wide range of composition, so, their use for healing requires appropriate knowledge.One of the most important world reference area for mud therapy has been accessed for sampling in different thermal centers (28) and also the exploiting site of raw clay has been studied. High resolution gamma spectrometry measurements have been acquired, compared with previous published data and discussed considering other compositional parameters.A clear increase of radionuclides of the 238U series characterize therapeutic muds respect to raw materials, 226Ra in particular. The scavenging of Ra from thermal waters is considered to occur after the precipitation of sulfate minerals (gypsum, barite) into the mud matrix, and several lines of evidence suggest that the repeated contact with thermal water (mud recycling) enhance the enrichment of Ra. A different scenario can be drawn for workers and for patients, as their contact with the mud is different for type and time. The dose arising from working in the area of therapeutic muds preparation and the dose to the skin of patients have been calculated.Even if Euganean therapeutic muds are richer in 226Ra respect to other similar materials, no radiological hazards emerged for workers who manage the preparation area, even in the most cautionary scenario. Also for patients, the contribution of Euganean mud therapy to the annual equivalent dose to skin is negligible, according to the cautionary elaboration done. Also considering literature data on the transcutaneous passage of chemical elements with geochemical affinity with Ra, no radiological hazard is detectable.

Geometry factor for in-situ soil contamination density estimation

A method is proposed for estimating the density of soil contamination with gamma-emitting radionuclides (Bc·m-2) in situ (in the field without sampling). The method allows to take into account the peculiarities of the distribution of radionuclides along the soil profile at a given site by the ratio of scattered and non-scattered photon fluxes. The scope of application has been expanded and the uncertainty of the previously developed method used for radiological examination of agricultural lands contaminated with 137Cs without sampling has been reduced. The proposed method of remote assessment of the pollution density practically does not introduce an additional error in comparison with the traditional method, which includes soil sampling and subsequent analysis in laboratory conditions. The duration of the spectrum set and its automatic processing at a 137Cs contamination density of more than 100 kBq·m-2 does not exceed 1 min.

Influence of phosphate fertilizers on the radioactivity of agricultural soils and tobacco plants in Kenya, Tanzania, and Uganda

Three brands of NPK fertilizers that contain variable concentrations of natural radioactivity are commonly used in tobacco plantations in Kenya, Tanzania, and Uganda. Tobacco plants are known for hyper-accumulation of natural radionuclides, particularly 238U. This study investigated if the elevated radioactivity in phosphate fertilizers could enhance radioactivity in soils and tobacco plant leaves. The 232Th, 238U, and 40K radionuclide levels in NPK-fertilized soils and tobacco leaves were measured using gamma-ray spectroscopy. The research included a one-year reference experiment with tobacco growing in plots, a ten-year semi-controlled experiment in well-managed tobacco farms, and a field survey of radioactivity in soils and tobacco leaves at three traditional tobacco fields in Migori (Kenya), Urambo (Tanzania), and Kanungu (Uganda). The findings demonstrated that soils and tobacco leaves exposed to NPK fertilizers with increased radioactivity had activity concentrations of 232Th, 238U, and 40K that were considerably higher (at all sites) than in the control samples (with no use of NPK fertilizers). As the continued application of NPK fertilizers raises concentrations of 232Th, 238U, and 40K in agricultural soils, the study assessed radiological risks for humans from exposure to agricultural soils enriched with phosphate fertilizers, and it was found to be below the exposure limit of 1 mSvy-1 suggested by the International Commission on Radiological Protection (ICRP). However, tobacco consumers, both by snuffing and smoking, may face significant radiological risks, as the snuffing and smoking resulted in effective doses that were 2.41 to 6.53 and 1.14 to 2.45 times greater than the average yearly dose that the general public receives from inhalation of natural radionuclides (United Nations Scientific Committee on Atomic Radiations estimates). Furthermore, the results indicate that the lifetime excess cancer risk for tobacco snuffers and smokers ranged from 5 × 10-5 to 24.48 × 10-3 and 2.0 × 10-5 to 9.18 × 10-3, respectively. The influence of phosphorus-derived fertilizer containing relatively high natural radioactivity, potential human radiation exposure, and radiological risk due to gamma radionuclides is estimated and discussed. The results reveal that applying phosphate fertilizers enhances natural radioactivity in soil and is subsequently influenced by soil to tobacco plant uptake. Therefore, the study recommends that countries use fertilizers with lower radionuclide content to conserve soil quality and reduce gamma-emitting radionuclides in tobacco plants.

Methods for express assessment of the radiation situation using a mobile laboratory in emergency situations

Methods for express assessment of the radiation situation in situ with the use of a mobile laboratory have been developed. During making decisions on protective measures application in the acute period of a radiological accident, the proposed methods make it possible to promptly assess the values of the volumetric activity of air in the breathing zone (Bq·m-3) and the contamination density of the territory with gamma-emitting radionuclides (Bq·m-2). These methods also allow to determine the activity (Bq) of the detected local radiation source. The scope of application has been expanded and the uncertainty of the previously developed method used for radiological survey of agricultural lands contaminated with cesium-137 without sampling has been reduced. It has been established that in the presence of not only caesium-137, but also caesium-134, cobalt-60, and iodine-131 on the radioactive trace, the proposed methodological approach makes it possible to quickly select the appropriate spectral regions for each pollutant and calibrate the detection units for the current radionuclide composition.

Using the gamma spectrometry method to determine the concentration of radon in samples of mineral radon water

The results of a study on the choice of the optimal measurement geometry, measuring capacity and method of sealing the measuring capacity for determining the concentration of radon-222 in samples of mineral radon water are presented. Studies of radon water samples were carried out in laboratory conditions on a stationary gamma spectrometer based on a semiconductor Ge(Li) detector. The concentration measurements in the samples were carried out in accordance with MVI. MN 3421-2010 “Methodology for measuring the volumetric and concentration of gamma-emitting radionuclides on gamma spectrometers with semiconductor detectors” for standard plastic vessels “Denta, 0.1 l” and “Marinelli, 1 l”, and glass containers with a volume of 0.5 l with lids for twisting and seaming. The results of the research showed that the leakage of radon from a glass container with a metal lid for sealing is minimal. This method of sampling and sealing the measuring vessel makes it possible to increase the accuracy of the presented measurement results by reducing the corrections for sample preparation when calculating the expanded measurement uncertainty. A glass container with a volume of 0.5 l with a metal cap for seaming was used to measure the concentration of radon in samples of mineral radon water taken from wells and a drinking fountain of the Radon sanatorium of Belagrozdravnitsa JSC (Dyatlovo District, Grodno Region). The concentration range was 760–2100 Bq/kg. The selected measuring container, the method of its sealing and the measurement geometry can be used for future measurements of the radon concentration in samples of mineral radon water taken in the sanatoriums of the Republic of Belarus.

Radionuclide metrology methods and analysis of the Joint Danube Survey 4 sediment samples

This low-level radionuclide metrology research work was carried out within the Joint Danube Survey 4 (JDS4), coordinated in 2018–2020 by the International Commission for the Protection of the Danube River (ICPDR). The gamma-emitting radionuclides of the sediment samples were analysed by low-level gamma-ray spectrometry. The activity concentration of 90Sr was determined by liquid scintillation counting (LSC) after isolating the radio-strontium using a new radiochemical separation method. The results of the radiometric analysis of 90Sr, 137Cs and naturally occurring radionuclides 40K, 210Pb, 226Ra, 228Ra in recent riverbed sediment are presented and discussed focused on public health.

Nanoparticles labeled with gamma-emitting radioisotopes: an attractive approach for in vivo tracking using SPECT imaging.

Providing accurate molecular imaging of the body and biological process is critical for diagnosing disease and personalizing treatment with the minimum side effects. Recently, diagnostic radiopharmaceuticals have gained more attention in precise molecular imaging due to their high sensitivity and appropriate tissue penetration depth. The fate of these radiopharmaceuticals throughout the body can be traced using nuclear imaging systems, including single-photon emission computed tomography (SPECT) and positron emission tomography (PET) modalities. In this regard, nanoparticles are attractive platforms for delivering radionuclides into targets because they can directly interfere with the cell membranes and subcellular organelles. Moreover, applying radiolabeled nanomaterials can decrease their toxicity concerns because radiopharmaceuticals are usually administrated at low doses. Therefore, incorporating gamma-emitting radionuclides into nanomaterials can provide imaging probes with valuable additional properties compared to the other carriers. Herein, we aim to review (1) the gamma-emitting radionuclides used for labeling different nanomaterials, (2) the approaches and conditions adopted for their radiolabeling, and (3) their application. This study can help researchers to compare different radiolabeling methods in terms of stability and efficiency and choose the best way for each nanosystem.

Current and upcoming radionuclide therapies in the direction of precision oncology: A narrative review

As new molecular tracers are identified to target specific receptors, tissue, and tumor types, opportunities arise for the development of both diagnostic tracers and their therapeutic counterparts, termed “theranostics.” While diagnostic tracers utilize positron emitters or gamma-emitting radionuclides, their theranostic counterparts are typically bound to beta and alpha emitters, which can deliver specific and localized radiation to targets with minimal collateral damage to uninvolved surrounding structures. This is an exciting time in molecular imaging and therapy and a step towards personalized and precise medicine in which patients who were either without treatment options or not candidates for other therapies now have expanded options, with tangible data showing improved outcomes. This manuscript explores the current state of theranostics, providing background, treatment specifics, and toxicities, and discusses future potential trends.