Thermal Neutron Irradiation Research Articles

High Energy and Thermal Neutron Sensitivity of Google Tensor Processing Units

In this article, we investigate the reliability of Google’s coral tensor processing units (TPUs) to both high-energy atmospheric neutrons (at ChipIR) and thermal neutrons from a pulsed source [at equipment materials and mechanics analyzer (EMMA)] and from a reactor [at Thermal and Epithermal Neutron Irradiation Station (TENIS)]. We report data obtained with an overall fluence of <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$3.41\times {10^{12}} {\mathrm {n/cm}}^{2}$ </tex-math></inline-formula> for atmospheric neutrons (equivalent to more than 30 million years of natural irradiation) and of <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$7.55\times {10^{12}} {\mathrm {n/cm}}^{2}$ </tex-math></inline-formula> for thermal neutrons. We evaluate the behavior of TPUs executing elementary operations with increasing input sizes (standard convolutions or depthwise convolutions) as well as eight convolutional neural networks (CNNs) configurations (single-shot multibox detection (SSD) MobileNet v2 and SSD MobileDet, trained with COCO dataset, and Inception v4 and ResNet-50, with ILSVRC2012 dataset). We found that, despite the high error rate, most neutron-induced errors only slightly modify the convolution output and do not change the detection or classification of CNNs. By reporting details about the error model, we provide valuable information on how to design the CNNs to avoid neutron-induced events to lead to misdetections or classifications.

Design, Synthesis and Biological Evaluation of Boron‐Containing Macrocyclic Polyamine Dimers and Their Zinc(II) Complexes for Boron Neutron Capture Therapy

AbstractBoron neutron capture therapy (BNCT) is considered to have potential for cancer therapy based on the nuclear reaction between boron (10B) atoms and thermal neutrons, yielding 4He2+ (α) and 7Li3+ ions. These heavy particles induce the destruction of biomolecules within short path length of 5–9 μm, resulting in a limited cytotoxic effect to 10B‐containing cells. Herein, we report on the design and synthesis of DNA‐targeting BNCT agents equipped with homo‐ and hetero‐dimeric macrocyclic polyamine units and their Zn2+ complexes. It was hypothesized that the dizinc(II) complexes of these ligands would recognize two adjacent thymidines (thymidyl(3'–5')thymidine), resulting in an efficient contact with DNA and an efficient breakdown of DNA upon thermal neutron irradiation. To test this hypothesis, we performed a DNA interaction study and a biological evaluation such as cytotoxicity and intracellular uptake activity using cancer and normal cells. BNCT experiments utilizing the corresponding 10B‐enriched compounds were also conducted.

Single Event Upsets Under Proton, Thermal, and Fast Neutron Irradiation in Emerging Nonvolatile Memories

In New Space, the need for reduced cost, higher performance, and more prompt delivery plans in radiation-harsh environments have motivated spacecraft designers to use Commercial-Off-The-Shelf (COTS) memories and emerging technology devices. This paper investigates the behavior of state-of-the-art memories manufactured in emerging technologies, including Ferroelectric Random-Access Memory (FRAM), Resistive Random-Access Memory (ReRAM), and Magnetic Random-Access Memory (MRAM), against radiation effects in static and dynamic modes. Radiation-ground tests were conducted under 15-MeV and 1-MeV protons, thermal and 14.8-MeV neutrons leading to various categories of radiation effects. Experimental results will show clear evidence of the robustness of bitcells manufactured using these emerging technologies against radiation, but at the same time, some susceptibility in these devices to suffer radiation effects when working in dynamic mode. Experimental results with the CY15B102Q and CY15B104Q FRAMs (Infineon Technologies), the MB85AS4MT, and MB85AS8MT ReRAMs (Fujitsu), and the MR10Q010CSC and MR25H40CDF MRAMs (Everspin) will be presented and discussed.

The structure, and magnetic properties of NiR0.05Fe1.95O4 (rare earth R=Sm, Gd): Effect of Thermal Neutron Radiation

The structure, and magnetic properties of NiR0.05Fe1.95O4 (rare earth R=Sm, Gd): Effect of Thermal Neutron Radiation

Comparison of FANT results using the ENDF/B-VII.1, JEFF-3.3 and TENDL2017 nuclear data libraries

FANT (Fuente Ampliada de Neutrones Térmicos; in Spanish) is a thermal neutron irradiation facility with an extended and very uniform irradiation area, that has been developed by the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Politecnica de Madrid (LMN-UPM). This device is a parallelepiped box made of high-density polyethylene (HDPE), moderator material, that uses an A95241m/B49e neutron source of 111 GBq nominal activity for irradiating materials. The facility design was previously optimized, and the neutron spectra were estimated by extensive calculations with the MCNP6.1 code and carrying out experimental measurements (Bedogni et al., 2017). The facility takes advantage of the scattering reactions of neutrons with the HDPE surfaces of the chamber, where the moderation process is effective, achieving relevant thermal neutron fluence rates. The main goal of this work has been to simulate and analyse the FANT system by Monte Carlo methods using the MCNP6.1 code, employing 3 different nuclear data libraries: ENDF/B-VII.1, JEFF-3.3 and TENDL 2017. The transport of thermal neutrons in HDPE, E < 1eV, has been calculated in all the cases taking into account the thermal S (α,β) treatment. The results achieved in this work have been compared with those previously obtained in the former development of FANT, using the MCNP6.1 code with the ENDF/B-VII.1 nuclear data, and experimental measurements. These results have shown that the JEFF-3.3 nuclear data library is the nuclear data library that provides of the best matching between the MCNP computational results, and the experimental data collected at FANT. Hence, the JEFF-3.3 nuclear data library seems to be the most correct library to design and benchmark thermal neutron activation devices.

Possible External Factors Determining Ultradian (4-20-min) Rhythms of Body Temperature.

The study examined the effect of passive magnetic shielding on the magnitude of rhythmic oscillations of body temperature (BT) with 4-20 min periods in mice and their correlation with similar oscillations in unshielded control group. A magnetic permalloy screen that 35-fold attenuates the total geomagnetic field and decreased the undulations of magnetic field with the periods of few minutes by 5 times, produced no effect on the mean amplitude of BT oscillations within the same period range, their spectral power, and the cross-spectral density of examined rhythms in comparison with the control (unshielded) mice. Thus, either the mice possess a very sensitive magnetic sensory system or there exists an external non-magnetic factor affecting rhythmicity of BT. The study advanced intensity of thermal neutron radiation near the Earth's surface known to reflect the flow of accelerated particles generated by the secondary cosmic rays as the external factor, which strongly correlates with BT rhythms revealed by cross-spectrum analysis.

ФИЛЬТР КАЛЬМАНА В ЗАДАЧЕ ОЦЕНКИ 8-ГРУППОВЫХ СПЕКТРОВ ЗАПАЗДЫВАЮЩИХ НЕЙТРОНОВ ПРИ ДЕЛЕНИИ 235U ТЕПЛОВЫМИ НЕЙТРОНАМИ

In the present work the estimation of the 8-group delayed neutron energy spectra emitted in the fission of 235U by thermal neutrons have been done. Aggregate delayed neutron spectra that were measured with high resolution in the different time intervals after the thermal neutron irradiation of the 235U sample presented in the IAEA reference database for beta-delayed neutron emission have been used for the estimation process. Due to the lack of the uncertainties for the spectra presented in this database and the necessity of this data in the process of estimation of delayed neutron group spectra at first the estimation of uncertainties of these spectra have been done. In the estimation process the following components of uncertainty have been considered: statistical; the component due to the neutron background; component due to the distinctive features of neutron spectra restoration process measured using spectrometer filled by helium-3 and also the component appearing due to introduction of the correction on the distortion of the neutron spectra as a result of passing through the lead sheilding. Estimation of spectra have been made using the technique based on the Kalman filter that allows to take into account the uncertainties of the input data. Estimation results are shown in the numerical and graphic form.

Production and measurement of fission product noble gases

Gaseous fission products have been produced via thermal neutron irradiation of a highly-enriched uranium target and extracted using a custom gas processing system for measurement on a prototype, high-resolution β − γ coincidence detection system. The gas was extracted and measured in two stages in order to measure the prompt and β−–delayed fission products. This paper presents an overview of the system used to produce gaseous fission products, and the results of the advanced coincidence spectrometry techniques used to identify and quantify decays from the radionuclides produced, including the noble gases 85Kr, 85mKr, 88Kr, 133Xe, 135Xe, 133mXe and 135mXe, as well as 133I and 88Rb. The measurements were validated by determination of the nuclear decay half-lives, specifically for the ground state decay of 135Xe, which was found to be 9.15(49) hours and consistent with the literature value. This work demonstrates the UK capability to produce gaseous radionuclides for quality assurance and calibration purposes in Radionuclide Laboratories supporting the Comprehensive Nuclear-Test-Ban Treaty (CTBT).

In vivo evaluation of PEGylated-liposome encapsulating gadolinium complexes for gadolinium neutron capture therapy

Gadolinium neutron capture therapy (GdNCT) is a form of binary radiotherapy. It utilizes nuclear reactions that occur when gadolinium-157 is irradiated with thermal neutrons, producing high-energy γ-rays and Auger electrons. Herein, we evaluate the potential of GdNCT for cancer treatment using PEGylated liposome incorporated with an FDA-approved MRI contrast agent. The clinical gadolinium complex (Gadovist®) was successfully encapsulated inside the aqueous core of PEGylated liposomes by repeated freeze and thaw cycling. At a concentration of 152 μM Gd, the Gd-liposome showed high cytotoxicity upon thermal-neutron irradiation. In animal experiments, when a CT26 tumor model was administered with Gd-liposomes (19 mg 157Gd per kg) followed by 20-min irradiation of thermal neutron at a flux of 1.94 × 104 cm−2 s−1, tumor growth was suppressed by 43%, compared to that in the control group, on the 23rd day of post-irradiation. After two-cycle GdNCT treatment at a 10-day interval, tumor growth was more efficiently retarded. On the 31st day after irradiation, the weight of the excised tumor in the GdNCT group (38 mg 157Gd per kg per injection) was only 30% of that of the control group. These results demonstrate the potential of GdNCT using PEGylated liposomes containing MRI contrast agents in cancer treatment.

Human Absorbed Dose Evaluation of [177Lu]Lu-IBA as a Bone Palliative Candidate.

The role of lutetium-177 among bone-seeking radionuclides in targeted therapy is noteworthy. The clinical pharmacokinetics of ibandronate (IBA) indicates that this bisphonate has powerful bone mineral affinity. The aim of this study was to evaluate of [177Lu]Lu-IBA efficacy as a new compound.The [177Lu]Lu-IBA was prepared by radiolabeling of IBA ligand to 177LuCl3 that was obtained by thermal neutron irradiation of enriched Lu2O3 sample. Produced [177Lu]Lu-IBA with high radiochemical purity was administered intravenously to mice. Biodistribution data were collected at 1, 4, 24, 48 h and 7 d post injections. With calculating accumulated activities in each organ and extrapolating mouse's organs to human's organs by the RADAR method and using OLINDA/EXM software the injected dose in various human organs was achieved.[177Lu]Lu-IBA was produced with radiochemical purity nearly 96 %. Its biodistribution data showed the high uptake and durability in the skeletal tissues without significant uptake in other major organs.The results showed that [177Lu]Lu-IBA has considerably good properties as a bone-seeking radiopharmaceutical and therefore can be a candidate for bone pain palliative therapy in skeletal metastases; however, further biological studies are still needed.

Nanometer-Sized Boron Loaded Liposomes Containing Fe3O4 Magnetic Nanoparticles and Tributyl Borate and Anti-Albumin from Bovine Serum Antibody for Thermal Neutron Detection.

A shortage in the supply of 3He used for thermal neutron detector makes researchers to find 3He alternatives for developing new neutron detectors. Here, we prepared a neutron-sensitive composite liposome with tributyl borate and encapsulating with Fe3O4@oleic acid nanoparticles (Fe3O4@OA NPs), methylene blue (MB), or anti-albumin from bovine serum (anti-BSA). The tributyl borate compound was characterized by Fourier transform infrared spectroscopy (FT-IR). In addition, the morphology, element compositions, and magnetic properties of the composite liposome were investigated with transmission electron microscopy (TEM), energy-dispersive X-ray spectroscopy (EDS), and vibrating sample magnetometer (VSM), respectively. The results indicated that a typical ellipsoidal magnetic liposome structure was obtained, and the lengths of the minor axis and major axis were 49 ± 1 nm and 87 ± 3 nm, respectively. Under thermal neutron irradiation, the structure of composite liposome was destroyed, and encapsulated reporter molecules were released, which was detected by ultraviolet–visible (UV–vis) spectroscopy and surface plasmon resonance (SPR) technology. The response of this sensor based on a destructive assay shows a good correlation with neutron doses. Besides, the sensor has a neutron to gamma-ray rejection ratio of 1568 at a thermal neutron flux rate of 135.6 n/cm2·s, which makes it a promising alternative to 3He.

Design, Synthesis, and Biological Evaluation of Boron-Containing Macrocyclic Polyamines and Their Zinc(II) Complexes for Boron Neutron Capture Therapy.

Boron neutron capture therapy (BNCT) is a binary therapeutic method for cancer treatment based on the use of a combination of a cancer-specific drug containing boron-10 (10B) and thermal neutron irradiation. For successful BNCT, 10B-containing molecules need to accumulate specifically in cancer cells, because destructive effect of the generated heavy particles is limited basically to boron-containing cells. Herein, we report on the design and synthesis of boron compounds that are functionalized with 9-, 12-, and 15-membered macrocyclic polyamines and their Zn2+ complexes. Their cytotoxicity, intracellular uptake activity into cancer cells and normal cells, and BNCT effect are also reported. The experimental data suggest that mono- and/or diprotonated forms of metal-free [12]aneN4- and [15]aneN5-type ligands are uptaken into cancer cells, and their complexes with intracellular metals such as Zn2+ would induce cell death upon thermal neutron irradiation, possibly via interactions with DNA.

Tumor-targeting hyaluronic acid/fluorescent carborane complex for boron neutron capture therapy

In cancer therapeutics, boron neutron capture therapy (BNCT) requires a platform for selective and efficient 10B delivery into tumor tissues for a successful treatment. However, the use of carborane, a promising candidate with high boron content and biostability, has significant limitations in the biomedical field due to its poor water-solubility and tumor-selectivity. To overcome these hurdles, we present in this study a fluorescent nano complex, combining fluorescent carborane and sodium hyaluronate for high boron concentration and tumor-selectivity. Tumor cells actively internalized the complex through binding hyaluronan to CD44, overexpressed on the tumor cell surface. Furthermore, the subcellular distribution of this complex could also be detected due to its fluorescent properties. Moreover, after thermal neutron irradiations, the complex produced excellent cytotoxicity, equal to or greater than that of the clinically-used BPA-fructose. Therefore, this novel complex could be potentially more suitable for BNCT than the boron agent.

Modeling long-term distribution of fast and thermal neutron fluence in degraded concrete biological shielding walls

Since neutron radiation can deteriorate mechanical properties of the concrete materials, it’s critical to obtain accurate neutron radiation levels in concrete structures during their service live. A two-group neutron diffusion model for fast and thermal neutron transport is developed in this study which considers the kinetic energy of the neutron more realistically. Based on the cross-property correlation theory, the variation of transport properties of concrete can be estimated using the degradation of mechanical properties of concrete, then, the thermal and fast neutron radiation fields with two representative energy levels as well as the thermal field in a concrete bioshield can be calculated. Coupled radio-thermo analysis of a section of simplified concrete bioshield was performed to 80 years as a case study, and the results were discussed and compared with the results from the one-speed model. The degradation of concrete induced by neutron radiation and elevated temperature can lead to considerable increases of thermal and fast neutron flux/fluence in the concrete. The profiles of thermal neutron flux/fluence are very different from the profiles of fast neutron flux/fluence. A proper treatment of the neutron energy dependence is needed to predict long-term neutron radiation levels in concrete biological shields accurately.

Effects of carbon impurity on tritium diffusion and helium formation in γ-LiAlO2 pellets: A first-principles study

Gamma-phase lithium aluminate (γ-LiAlO2) in the form of annular pellets is used as a breeding material in tritium-producing burnable absorber rods (TPBARs) for the production of tritium by thermal neutron irradiation of 6Li. Significant radiation damage occurs in γ-LiAlO2 due to neutrons, and tritium and helium (He) nuclei, which recoil through the crystal. The radiation-damaged crystal is rich with vacancies and impurities such as carbon (C) that can act as tritium trapping sites. The presence of C impurities can hinder 3H diffusivities significantly. Here, we studied the effect of C impurities on 3H diffusivity and energy barriers in γ-LiAlO2 using first-principles density functional theory. In addition, we studied the He diffusion in an undefective γ-LiAlO2. We calculated the energy barrier for diffusion in γ-LiAlO2 to be 0.98 eV for substitutional 3H in the presence of a C impurity. At 600 K, the corresponding diffusion coefficient was calculated to be 7.98×10-14m2/s. Similarly, we calculated the energy barrier for He diffusion to be 0.12 eV, which was along the crystallographic c-direction. The corresponding diffusion coefficient for He at 600 K was calculated to be 6.8×10-7m2/s. This work may open further theoretical and experimental avenues on impurity effects and release of He from γ-LiAlO2.

Fructose-functionalized polymers to enhance therapeutic potential of p-boronophenylalanine for neutron capture therapy

In boron neutron capture therapy (BNCT), boron drugs should accumulate selectively within a tumor and be quickly cleared from blood and normal organs. However, it is usually challenging to achieve the efficient tumor accumulation and the quick clearance simultaneously. Here we report the complex composed of a fructose-modified poly(ethylene glycol)-poly(l-lysine) block copolymer and p-boronophenylalanine, termed PEG-P[Lys/Lys(fructose)]-BPA, as a boron delivery system permitting selective accumulation within the target tumor with quick clearance from normal organs as well as blood. Our PEG-P[Lys/Lys(fructose)]-BPA could be internalized into tumor cells through LAT1 amino acid transporter-mediated endocytosis and retain in the targeted cells, thereby accomplishing more efficient accumulation and retention in a subcutaneous tumor than clinically used fructose-BPA complexes. Importantly, the moderately cationic property of the polymer facilitated renal clearance and PEG-P[Lys/Lys(fructose)]-BPA exhibited high accumulation contrast between the target tumor and the blood/normal organ. Finally, upon thermal neutron irradiation, PEG-P[Lys/Lys(fructose)]-BPA significantly inhibited the tumor growth in mice. PEG-P[Lys/Lys(fructose)]-BPA may be a promising boron delivery system for BNCT.

Suppression of Tumor Growth in a Rabbit Hepatic Cancer Model by Boron Neutron Capture Therapy With Liposomal Boron Delivery Systems.

Tumor cell destruction by boron neutron capture therapy (BNCT) is attributed to the nuclear reaction between 10B and thermal neutrons. The accumulation of 10B atoms in tumor cells without affecting adjacent healthy cells is crucial for effective BNCT. We previously reported that several types of liposomal boron delivery systems (BDS) delivered effective numbers of boron atoms to cancer tissues, and showed tumor-growth suppression after thermal neutron irradiation. In the present study, we examined the effects of BNCT after intra-arterial infusion of 10B-borono-dodecaborate (10BSH) by liposomal BDS in rabbit hepatic cancer models. We prepared 10BSH-entrapped transferrin-conjugated polyethylene glycol liposomes constructed with distearoyl-boron lipid (TF-PEG-DSBL), and performed thermal neutron irradiation at the Kyoto University Institute for Integrated Radiation and Nuclear Science after intra-arterial infusion into rabbit VX-2 hepatic tumors. Concentrations of 10B in VX-2 tumors on delivery with TF-PEG-DSBL liposomes reached 25 ppm on day 3 after the injection. Tumor growth was suppressed by thermal neutron irradiation after intra-arterial injection of this 10BSH-containing liposomal BDS, without damage to normal cells. The present results demonstrate the applicability of 10B-containing TF-PEG-DSBL liposomes as a novel intra-arterial boron carrier in BNCT for cancer.

Effects of thermal neutron radiation on a hardware-implemented machine learning algorithm

Hardware-implemented machine learning algorithms are finding their way in various domains, including safety-critical applications. This has demanded these algorithms to perform correctly even in harsh environmental conditions, such as in avionics altitudes. Support Vector Machine (SVM) is an important Machine Learning that has been target of hardware implementation in recent years. This is the first work to asses both Binary and Multiclass SVMs under thermal neutron radiation, a type of particle noticeably present in high altitudes. A fault injection campaign along with a radiation test with the D50 thermal neutron source, at the Intitut Laue-Languevin, has been performed. The results show a high intrinsic fault tolerance for both varieties of the SVM algorithm, especially for the Multiclass SVM.

A NMR and SANS study of alkali-borosilicate behaviour under thermal neutron irradiation

The internal structure of several alkali-borosilicate glasses has been studied when exposed to a high thermal neutron flux. More specifically, the different glasses we are interested in are widely used around the globe for neutron guide manufacturing and show drastically different resistance to irradiation. Samples were irradiated with the thermal flux from T4 experimental tube in ILL’s High Flux Reactor up to a fluence of several 1017 n/cm2. The experimental tools employed for the structural analysis were Nuclear Magnetic Resonance (NMR) and Small Angle Neutron Scattering (SANS). NMR measurements allowed to detect the modification of atoms’ close environment and these results have been correlated to evolutions at macroscopic scale. In addition, neutron scattering measurements have demonstrated the possibility to detect phase segregation in a zinc-alkali-borosilicate.

Carbonaceous deposits on aluminide coatings in tritium-producing assemblies

Abstract Co-deposition of carbon atoms with hydrogen isotopes and hydrogenated carbon radicals and molecules is recognized as the main mechanism for tritium retention in the graphite walls of the previous tokamak fusion devices. Significant tritium retention would be a serious concern for safe and economic long-term operation of future fusion test reactors and fusion energy systems. Similar deposits are observed on the surface of the engineered components in a tritium-producing assembly, known as a Tritium-Producing Burnable Absorber Rod (TPBAR). Characterization of the deposits can help understand the tritium transport, accumulation history and distribution in TPBARs. This study reports our recent results from the carbonaceous deposits formed on an aluminide-coated cladding in the lower plenum of a TPBAR following thermal neutron irradiation. The observed deposits are amorphous in nature, consisting of flakes of interconnected nanoscale features. They contain primarily double-bonded carbon (e.g., alkene) and carbonyl carbon, as well as a minor fraction of aliphatic carbon, all of which are likely tritiated. A similar co-deposition process that occurred in previous fusion devices is responsible for the formation and growth of the carbonaceous deposits.