Neutron Activation Research Articles

Radiation shielding parameterizations of FeSO4, CuSO4, NiSO4 and ZnSO4 Compounds: using (XRF) technique & Monte Carlo FLUKA approach

The mass attenuation coefficient (MAC) for different sulphate compounds can be estimated by using the Energy Dispersive X-ray Fluorescence (EDXRF), also known as X-ray Fluorescence (XRF) technique. The X-ray photons emitted have different energies depending on incident photon energy, atomic weight, and molecular structure of tested material. The excitation energy of the gamma rays source with 59.53 keV was obtained by using 241Am (40 µci). The (MAC) for sulphate compounds of a different element (Fe, Ni, Cu, Zn) have been calculated by measuring the intensity difference for kα in pure elements and their compounds. The determined results showed that the maximum value for (µm) was in FeSO4. These results are consistent with the theoretical value obtained by the XCOM software in addition to investigating the wide energy response of photon interaction with the introduced compounds using the FLUKA Monte Carlo simulation software. The mass attenuation coefficient (MAC) of these compounds is numerically evaluated in the energy range 0.015-15 MeV using the FLAIR code. The computed (µm) is used to generate significant radiation protection factors such as the linear attenuation coefficient (LAC), half-layer value (HVL), effective (Zeff), and equivalent (Zeq) atomic number. For studying the shielding effectiveness and efficiency, for fast and thermal neutron radiation, the removal cross-section ƩR was given.

Investigation of the neutron radiation fields inside the accelerator tunnel during operation of the Swiss Light Source (SLS)

The Swiss Light Source (SLS) is a third-generation synchrotron light source with an electron energy of 2.4 GeV. It consists of a linear accelerator, a booster and a storage ring providing light for various applications. As SLS is a high-energy accelerator, its operation is accompanied with production of ionizing radiation fields, including neutrons. This leads to additional challenges from a radiation protection point of view. The long-term investigation of the radiation fields at this accelerator facility can provide useful information for the residual activation studies and optimization of shielding. This work describes measurements of the neutron radiation fields inside the tunnel and results of this study.

3D reconstruction of an inertial-confinement fusion implosion with neural networks using multiple heterogeneous data sources.

3D asymmetries are major degradation mechanisms in inertial-confinement fusion implosions at the National Ignition Facility (NIF). These asymmetries can be diagnosed and reconstructed with the neutron imaging system (NIS) on three lines of sight around the NIF target chamber. Conventional tomographic reconstructions are used to reconstruct the 3D morphology of the implosion using NIS [Volegov et al., J. Appl. Phys. 127, 083301 (2020)], but the problem is ill-posed with only three imaging lines of sight. Asymmetries can also be diagnosed with the real-time neutron activation diagnostics (RTNAD) and the neutron time-of-flight (nToF) suite. Since the NIS, RTNAD, and nToF each sample a different part of the implosion using different physical principles, we propose that it is possible to overcome the limitations of too few imaging lines of sight by performing 3D reconstructions that combine information from all three heterogeneous data sources. This work presents a new machine learning-based reconstruction technique to do just this. By using a simple physics model and group of neural networks to map 3D morphologies to data, this technique can easily account for data of multiple different types. A simple proof-of-principle is presented, demonstrating that this technique can accurately reconstruct a hot-spot shape using synthetic primary neutron images and a hot-spot velocity vector. In particular, the hot-spot's asymmetry, quantified as spherical harmonic coefficients, is reconstructed to within ±4% of the radius in 90% of test cases. In the future, this technique will be applied to actual NIS, RTNAD, and nToF data to better understand 3D asymmetries at the NIF.

Novel deuterium-tritium (DT) neutron activation diagnostics for increased neutron yield operations at Sandia's Z-facility (invited).

As inertial confinement fusion experiments at Sandia National Laboratories' Z-facility begin using deuterium-tritium (DT) fuels, the expected DT-neutron yields are expected to increase many orders of magnitude. This brings about the need for diagnostics that have a significantly higher dynamic range of operation and ability to obtain yields where there will be significant radiation holds. Using the current activation diagnostic infrastructure at the Z-facility, a pair of activation diagnostics are being developed. The first is fluorine activation, which will be used in a similar manner to current copper activation diagnostics that are fielded in a rabbit for quick removal from the experiments without opening the vacuum experiment containment. The second is a prompt DT-neutron detector that exploits the activation of oxygen with similar operation characteristics as the current Be-probes fielded at Z. We will discuss the design of this pair of instruments, along with calibration work performed at Sandia's Ion Beam Laboratory in support of the development and anticipated instrument performance.

Assessing the efficacy of some heavy-metal infused concrete mixtures in gamma-ray and neutron shielding applications

This study examines the radiation shielding properties of sixteen diverse concrete types encompassing both gamma-ray and neutron radiation. Concrete, a widely used material due to its low cost, high density, and efficient shielding capabilities, is investigated to determine how its varying compositions impact its ability to attenuate ionizing radiation. Utilizing the Phy-X/PSD software, the research analyses key parameters like mass attenuation coefficients, linear attenuation coefficients, and half-value layers, among others, to assess each concrete type's shielding efficiency. The findings reveal that concretes containing heavy metals such as iron and barium exhibit enhanced performance in absorbing photons, thus providing superior protection against radiation. Iron-Portland concrete demonstrated a high density of 5.80 g/cm³ and exhibited a mass attenuation coefficient (MAC) of 35.14 cm2/g at 0.1 MeV, significantly higher than MAC of ordinary concrete (i.e., 17.24 cm2/g). Significantly, Iron-Portland and Barite Concrete are highlighted for their exceptional shielding abilities, with Iron-Portland showing a fast neutron removal cross-section (ΣR) of 14.29 cm−1, compared to 11.11 cm−1 for ordinary concrete. It can be concluded that the high elemental mass fraction of iron (88.12 wt%) in Iron-Portland concrete, along with its significant density of 5.80 g/cm3, makes it the most advantageous for gamma-ray and neutron shielding applications due to its superior absorption and attenuation capabilities.

Effect of ZrO2 on Radiation Permeability Properties of Polypropylene

The study investigates the radiation permeability properties including mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), tenth value layer (TVL), half value layer (HVL), fast neutron cross section (FNRC), and mean free path (MFP) of polypropylene (PP) polymer, as well as the produced polymer matrix composites (PP+5% ZrO2, PP+10% ZrO2, PP+15% ZrO2). The studied materials were examined by considering their effect on radiation permeability against gamma and neutron radiation. Additionally, powder size, Archimedes principle (density), XRD, DSC, ATR, and DTA-TG analyses were performed. According to the radiation permeability results of the studied four materials, PP + 15% ZrO2 was found to have the highest LAC values, while PP was found to have the lowest LAC values. The FNRC values of the PP, PP+5% ZrO2, PP+10% ZrO2, and PP+15% ZrO2 materials were found to be 10.038 cm-1, 12.651 cm-1, 15.002 cm-1, and 17.091 cm-1, respectively. The most suitable material for gamma and neutron shielding was found to be 15% ZrO2 reinforced material.

Emerging techniques for the trace elemental analysis of plants and food-based extracts: A comprehensive review

This comprehensive review investigates the dynamic landscape of trace elemental analysis methodologies applied to plants and food-based extracts. The exploration spans from the inception of techniques to the latest procedures, contributing to heightened precision and sensitivity in elemental detection. According to the WHO, herbal plants and medicine from varied soil compositions serve as crucial therapeutic agents for 70–80 % of the world's population. Yet, their susceptibility to trace element toxicity poses a significant risk to human health. Rising population and increased food demands have led to environmental pollution, contaminating the food chain through unintended activities like industrialization, mining, and pesticide production. The elemental composition of plants and derived extracts is central to comprehending nutritional profiles, evaluating product quality, and ensuring food safety. Methodological advancements, progressing from manual procedures to sophisticated technologies such as X-ray fluorescence (XRF), neutron activation analysis (NAA), inductively coupled plasma optical emission spectroscopy (ICP OES), and inductively coupled plasma mass spectrometry (ICP-MS), are delineated. Recent strides in paper-based electrochemical sensors are highlighted for their distinctive capabilities and elucidation of associated advantages and limitations.Moreover, the review delves into innovative sample preparation methodologies, encompassing microwave-assisted digestion and solid-phase microextraction, to amplify the efficiency of elemental extraction and subsequent analysis. Integrating data analytics and machine learning in elucidating complex elementary datasets is explored, underscoring the potential for heightened accuracy and automation in trace elemental analysis. This review compiles literature data, summarizing sample preparation methods for various herbal parts (roots, soil, stems, bark, fruits, food). Standard protocols from WHO, United States Pharmacopeia-National Formulary (USP-FR), Ayurveda, Yoga and Naturopathy, Unani, Siddha, and Homeopathy (AYUSH) are considered. Lead, Cadmium, Mercury, and Arsenic are the primary toxic elements of concern in herbal medicines. This review furnishes valuable insights tailored for researchers, analysts, and policymakers actively involved in advancing the domain of trace elemental analysis in plants and food-based extract.

Micaceous Mindsets: Chemical characterization of classic period utility wares at multiple sites along the Rio Grande

Micaceous utility wares are commonly found at Ancestral Pueblo villages in the Rio Grande region, yet they have received relatively little attention compared to contemporary glaze wares. This lack of attention is unfortunate, because utility wares were a common component of daily Pueblo activities and are shown to have been involved in complex exchange schemes. Neutron activation analysis is used to chemically characterize micaceous utility sherds recovered from seven Classic Period (AD 1300–1600) sites located along the Rio Puerco and Rio Grande between the modern towns of Santa Fe and Socorro, New Mexico. The resulting distribution patterns broadly indicate heterogeneous procurement and/or manufacturing practices from site-to-site over the three centuries examined; however, a shared distribution between the Rio Puerco and Central Rio Grande is distinguishable. This relationship is evaluated and interpreted under a communities of practice framework, and bears to question how the manufacture, distribution, and use of micaceous utility wares elsewhere may be explored with this approach.

Developing a trial design to establish BNCT as clinical application: insight for the national italian center for oncological hadrontherapy (CNAO)

PurposeBoron Neutron Capture Therapy (BNCT) represents an advanced radiation therapy capable of selectively killing tumor cells. It operates on a dual therapy approach, utilizing boronated agents that preferentially deliver boron-10 to tumors, followed by neutron irradiation. This leads to the emission of two ionizing particles. These particles expend all their energy over a distance comparable to the diameter of a cell and can cause irreparable damage to DNA when passing through the nucleus.MethodsThis paper outlines the approach taken by the Italian National Cancer Center for Oncological Hadrontherapy (CNAO) to achieve BNCT certification for clinical applications within the EU regulatory framework.ResultsThe existing literature reports excellent outcomes for many unresectable and recurrent tumors, especially in head and neck cancer (HNC).ConclusionsThe paper seeks to clarify the rationale and methods for formulating a clinical trial design to meet these objectives.

Evaluation of relative biological effectiveness for diseases of the circulatory system based on microdosimetry.

In the next decade, the International Commission on Radiological Protection (ICRP) will issue the next set of general recommendations, for which evaluation of relative biological effectiveness (RBE) for various types of tissue reactions would be needed. ICRP has recently classified diseases of the circulatory system (DCS) as a tissue reaction, but has not recommended RBE for DCS. We therefore evaluated the mean and uncertainty of RBE for DCS by applying a microdosimetric kinetic model specialized for RBE estimation of tissue reactions. For this purpose, we analyzed several RBE data for DCS determined by past animal experiments and evaluated the radius of the subnuclear domain best fit to each experiment as a single free parameter included in the model. Our analysis suggested that RBE for DCS tends to be lower than that for skin reactions, and their difference was borderline significant due to large variances of the evaluated parameters. We also found that RBE for DCS following mono-energetic neutron irradiation of the human body is much lower than that for skin reactions, particularly at the thermal energy and around 1MeV. This tendency is considered attributable not only to the intrinsic difference of neutron RBE between skin reactions and DCS but also to the difference in the contributions of secondary γ-rays to the total absorbed doses between their target organs. These findings will help determine RBE by ICRP for preventing tissue reactions.

Measurements of concentrations of some elements in the meat and skin of farmed and marine fish of the Persian Gulf using the neutron activation analysis technique

Measurements of concentrations of some elements in the meat and skin of farmed and marine fish of the Persian Gulf using the neutron activation analysis technique

Некоторые закономерности накопления микроэлементов в листьях липы (Tilia cordata Mill.) и берёзы (Betula alba L.)

The purpose of the work: to study the patterns of background accumulation of trace elements during the spring-summer-autumn season in the vegetative organs (leaves) of the heart-shaped linden (Tilia cordata Mill.) and white birch (Betula alba L.). Samples were taken on the territory of the Main Botanical Garden of the Russian Academy of Sciences during one season of 2018 from the same tree with an interval of 10–12 days, starting from the opening of the bud (end of April) right up to the time of leaf fall. Soil samples were also taken from birch and linden growing areas. The samples were analyzed in the laboratory of Chemical analytical methods of the GIN RAS using X-ray fluorescence analysis (XRF), instrumental neutron activation analysis (INАA) and atomic absorption spectrometry of cold vapor (AA). The concentration of trace elements in the selected soil samples corresponds to the concept of “background” contents. Two types of trace elements’ distribution in linden and birch leaves during the season have been revealed. The first type is a uniform accumulation of trace elements with a maximum at the end of the season (Na, Ca, Cr, Fe, Co, Br, Sb, La). The second type of distribution is characterized by a maximum concentration of trace elements in the middle of the season with a decrease in concentration by the time of leaf fall (K, As, Zn, Cd, Pb). It should be noted that the range of changes in the concentration of trace elements during the season in both cases can reach 10–15 times. We recommend to take samples of vegetation (leaves) as soon as possible in the middle of the summer season, and to use samples taken at the same time in the same area as “background”.

Rare earth elements as tracers: A study on post-wildfire effects in soil by neutron activation analysis

This study investigated using rare earth elements as tracers to study wildfire impacts. The study area was Antalya, located in the Mediterranean region of Türkiye. This region is known for the frequent occurrence of wildfires, which cause significant damage to the flora and fauna of the area. A series of wildfires occurred in the region in 2016. Soil samples were collected from the affected areas to understand these wildfires' impact better. Instrumental neutron activation analysis was used to analyze the samples. The study found that the north-facing aspect had higher concentrations of rare earth elements. This could be because north-facing aspects are cooler and more humid, with less erosion, leading to better ecological restoration and less transportation of rare earth elements.

Gold content determination in small core-samples by instrumental neutron activation analysis

Application of instrumental neutron activation analysis (INAA) based on the relative method of concentration standardization was considered to determine Au content in small solid core-samples of the gold-bearing ores and rocks up to 10 g of the mass. The small core-samples about 10 mm in diameter and 22-23 mm in length were cut from the previously collected ore lumps or in-situ using a handheld drilling rig. The studied small core-samples and the polyethylene capsules of the same dimensions filled up with the corresponding certified reference material (CRM) were irradiated for 2 min by a lower density neutron flux with the help of the automated pneumatic transport system (PTS). Maximum mass and dimensions of the core-samples corresponded to the PTS design and to the conditions of its safe operation. A special device was made to fix the transport capsules in the stable counting geometry making possible to eliminate the influence of the neutron flux gradient during irradiation. Due to the substantial differences in CRM and solid sample densities, corrections for neutron self-shielding and for gamma-ray self-absorption by the core-samples were applied. The method was tried to analyze Au content in 170 small core-samples presenting different gold-bearing ores and country rocks from the Kazakhstan’s gold-barite-polymetallic deposit Maikain. This approach, rather simple methodically and requiring no unique equipment, can be used to assess gold resources together with the methods of geostatistics.

Oxide particles in oxide dispersion strengthened steel neutron-irradiated up to 158 dpa at Joyo

We investigated the stability of oxide nano particles in oxide dispersion-strengthened (ODS) steel, which is a promising candidate material for next-generation reactors, under neutron irradiation at high temperature to high doses. MA957, a 14Cr-ODS steel, was irradiated with Joyo in Japan Atomic Energy Agency under irradiation conditions of 130 dpa at 502 ºC, 154 dpa at 589 ºC, and 158 dpa at 709 ºC. Three-dimensional atom probe (3D-AP) and transmission electron microscope (TEM) observation were performed to characterize the oxide particles in the ODS steels. A high number density of Y-Ti-O particle was observed in the unirradiated and irradiated samples. Almost no change in the morphology of the oxide particles, i.e. average diameter, number density, and chemical composition, has been observed in the samples irradiated to 130 dpa at 502 ºC and to 154 dpa at 589 ºC. A slight decrease in number density was observed in the sample irradiated to 158 dpa at 709 ºC. The hardness of any of the irradiated samples was almost unchanged from that of the unirradiated sample. It was revealed that the oxide particles existed stable, and the strength of the material was sufficiently maintained even after being neutron irradiated to high dose of ∼160 dpa at high temperature up to 700 ºC.

Radiation Techniques for Tracking the Progress of the Hydrometallurgical Leaching Process: A Case Study of Mn and Zn

With advancements in hardware and software, non-destructive radiometric analytical methods have become popular in a wide range of applications. A typical case is the study of the leaching process of metals from mineral ores and mine tailings. The objective of the current study was to develop a radiometric method based on neutron activation analysis (NAA), in particular, delayed gamma neutron activation analysis (DGNAA), to monitor the process of Mn and Zn leaching from Ti ore, Cu mine tailings, and Zn-Pb mine tailings. The DGNAA method was performed using a neutron source: a deuterium-tritium (D-T) neutron generator for Mn and a MARIA research nuclear reactor for Zn. Laboratory-scale Mn leaching from Ti ores, Cu tailings, and Zn-Pb tailings was investigated using delayed gamma-rays of 56Mn (half-life of 2.6 h). The dissolution efficiencies of Mn were found to increase with interaction time and HCl concentration (1 to 5 M) and to vary with the leaching temperature (22.5 to 110 °C). Such results were found to agree with those obtained by total reflection X-ray fluorescence (TXRF) spectrometry for the same samples. 65Zn (half-life of 244 days) was chosen to investigate real-time/online leaching of Zn in Ti ore, Cu tailings, and Zn-Pb tailings. During online monitoring, Zn recovery was also reported to increase with increased leaching time. After approximately 300 min of leaching, 80%, 79%, and 53% recovery of Zn in Zn-Pb tailings, Ti ore, and Cu tailings, respectively, were reported. Theoretically, developed mathematical prediction models for 65Zn radiotracer analysis showed that the spherical diffusion model requires much less time to attain saturation compared to the linear diffusion model. The results of NAA for Zn were compared with those obtained by handheld X-ray fluorescence (handheld-XRF) and TXRF analysis. The analyzed samples encompassed leached Ti ore, Cu tailings, and Zn-Pb tailings which were subjected to different conditions of leaching time, temperature, and HCl concentrations. The XRF analysis confirmed that the leaching efficiencies of Zn rise with the increase in leaching time and HCl concentration and fluctuate with leaching temperature. The developed approach is important and can be applied in laboratories and industrial setups for online monitoring of the recovery of any element whose isotopes can be activated using neutrons. The efficiency of the metal-recovery process has a direct impact on the normal operation and economic advantages of hydrometallurgy.

Albumin nanoparticle electrostatically loaded with highly anionic Gd-thiacalixarene complex for MRI-guided neutron capture therapy

As a neutron capture therapy (NCT) agent, 157Gd garners significant attention due to the largest neutron capture cross section, emission of γ rays and Auger electrons, and facilitation of magnetic resonance imaging-guided NCT. Owing to its high kinetic stability, 1H relaxivity, and facile conjugation to albumin via electrostatic interactions, the negatively charged Gd3TCAS2 complex {TCAS = thiacalix[4]arene-p-tetrasulfonate (TCAS)} was incorporated into albumin nanoparticles (ANPs) in various configurations, including shell, core, and core-shell types, contingent on the positioning of Gd3TCAS2 within the ANP. The characteristics of the ANPs optimized with respect to loading capacity (LC) were explored, all of which demonstrated particle sizes suitable for passive delivery. The LC of Gd3TCAS2 per ANP increased in the following order: shell (1.1 %) < core (1.4 %) < core-shell (8.1 %). The leakage of Gd3TCAS2 after 7 d of storage was approximately 2 % for all ANPs, indicating stable Gd3TCAS2 loading. The 1H relaxivity (e.g., core-shell: r1 = 10.7 mM–1s–1) surpassed that of the Gd3TCAS2 complex alone (3.15 mM–1s–1). The luminescence emanating from Tb in MCF-7 cells co-cultured with Tb3TCAS2-loaded ANPs corroborated this cellular uptake. Gd uptake into MCF-7 cells via Gd3TCAS2-loaded ANPs was most pronounced for core-shell ANP at 1.33 ± 0.06 nmol/106 cells. The cytotoxicity of Gd3TCAS2-loaded ANPs was mitigated compared to free Gd3TCAS2 (CC50 = 52 µM), with shell and core-shell ANPs demonstrating nearly 100 % cell survival even at 50 µM. Cell viability post thermal neutron irradiation revealed the highest NCT efficacy for free Gd3TCAS2, attributed to its elevated cellular uptake (15.71 ± 0.57 nmol/106 cells). Core-shell ANP also exhibited a notable reduction in cell viability relative to the control, validating their potential as a promising GdNCT agent.

Preliminary study of a compact pulsed deuterium-deuterium neutron generator with a vacuum arc ion source and a linear induction accelerator

The pulsed neutron beam combined with the time-of-flight (TOF) technique has shown great value in many scientific research and application fields. Most of the neutron-based material identification and interrogation systems require an intense pulsed neutron beam. Time resolved prompt gamma neutron activation analysis (T-PGNAA) is an effective analytical method to greatly suppress interference from the other elements or the neutron shields of the detectors. To develop T-PGNAA method in a compact accelerator neutron source, a novel intense pulsed deuterium-deuterium (D-D) neutron generator based on a linear induction accelerator (LIA) was introduced. The generator has four major components: a vacuum arc ion source with deuterated electrode, a diode accelerator structure, a self-biased voltage secondary electron suppressed structure and a deuterated metal target. The present study characterizes the performance of the neutron generator with respect to neutron yield, the ionic current, beam profile, and beam composition as a function of the acceleration voltage at various discharge currents. Monoenergetic neutrons (2.5 MeV) are produced with a yield of ∼104 n/p and a pulse width of ∼100 ns using about 200 kV of induction acceleration voltage at 10−4 Pa vacuum environment. In this study, we will discuss various physical and technical issues related to the components of the neutron generator and the operation and merits of the novel neutron generator.

Investigation of ferrochrome slag utilization in wet mix shotcrete: Mechanical strength and radiation shielding performance

In this study, wet-mix shotcrete specimens were produced by substituting natural aggregate (NA) with ferrochrome slag aggregate (FS). Volumetrically, the amount of NA was reduced by 25%, 50%, 75% and 100% and a corresponding amount of FS aggregate was added. The physical, mechanical, durability and radiation shielding properties of the specimens were analysed. The gamma radiation performance was determined using energies 133Ba, 137Cs, 60Co and 22Na (ranging from 276.5 keV to 1332.5 keV) and a high-purity germanium HPGe detector system. The neutron radiation performance of the shotcrete specimens was obtained using FLUKA simulation. The WinXCOM interface was used for theoretical calculations, while the FLUKA Monte Carlo code was used for simulation calculations, and the data obtained were compared. It was observed that shotcrete mixtures having up to 50% ferrochrome slag aggregate showed a significant increase in mechanical properties. In radiation shielding performances, linear attenuation coefficient (μ), half-value layer (HVL), Tenth-value layer (TVL), mean free path (MFP) and radiation protection efficiency (RPE) parameters increased with increasing ferrochrome slag aggregate ratio, while mass attenuation coefficient (μ⁄ρ) values remained almost constant. It was experimentally determined that the 5 cm thickness shotcrete produced had RPE values of 75% and 50% at low (276.4 keV) and high (1332.5 keV) energies, respectively. It was concluded that the use of 50% ferrochrome slag aggregate has a positive effect on the mechanical properties of shotcrete mixtures. Additionally, ferrochrome slag-reinforced shotcrete is a good gamma and neutron radiation shielding material.

Dosimetric studies of e-, γ-, n- Irradiation fields of the M-30 microtron (18.5 mev)

The results of the implementation and study of the radiation characteristics of high-energy electron (e-), gamma (γ-), and neutron (n-) radiation fields of the M-30 microtron with a maximum energy of 18.5 MeV are presented. Dosimetric characteristics were studied using the method of thermally stimulated luminescence (TSL) and using samples TLD-100H (LiF: Mg,Cu,P) and TLD-500K (Al2O3:C). Three e-, γ-, and n-experiments were performed at the same M-30 electron flux; the dosimetric indicators Yγ,n;e = Dγ,n/De, where Dγ,n is the intensity of the dosimetric peaks of TSL after γ- or n-irradiation, and De is, respectively, e-irradiation. We discuss the relative stability of these dosimeters' Yγ,e parameters at gamma irradiations and the presence of a partial correlation of Yn,e values in neutron fields. The latter is associated with the peculiarity of radiation defect formation in the material of dosimeters when interacting with nuclear particles of different types. The research results confirm the general ideas about the physics of electron radiation conversion into beams of nuclear particles of different natures. The data obtained are important in developing methods for dosimetric support of radiation technologies that use beams of mixed high-energy nuclear radiation, particularly for radiation therapy.