10B Concentration Research Articles

Peptide-functionalized gold nanoparticles for boron neutron capture therapy with the potential to use in Glioblastoma treatment

Glioblastoma is a highly aggressive glioma with limited treatment options. Boron neutron capture therapy (BNCT) offers a promising approach for refractory cancers, utilizing boron-10 (10B) and thermal neutrons to generate cytotoxic particles. Effective BNCT depends on selective targeting and retention of 10B in tumors. Current BNCT drugs face issues with rapid clearance and poor tumor accumulation. To address this, we developed gold nanoparticles (AuNPs) functionalized with cyclic arginine-glycine-aspartic acid (cRGD) peptides as a nanocarrier for Sodium Mercaptododecaborate (BSH), resulting in AuNPs-BSH&PEG-cRGD. In vitro, AuNPs-BSH&PEG-cRGD increased 10B content in GL261 glioma cells by approximately 2.5-fold compared to unmodified AuNPs-BSH&PEG, indicating enhanced targeting due to cRGD's affinity for integrin receptor αvβ3. In a subcutaneous glioma mouse model, 6 h post-intratumoral administration, the 10B concentration in tumors was 17.98 μg/g for AuNPs-BSH&PEG-cRGD, significantly higher than 0.45 μg/g for BSH. The tumor-to-blood (T/B) and tumor-to-normal tissue (T/N) ratios were also higher for AuNPs-BSH&PEG-cRGD, suggesting improved targeting and retention. This indicates that AuNPs-BSH&PEG-cRGD may enhance BNCT efficacy and minimize normal tissue toxicity. In summary, this study provides a novel strategy for BSH delivery and may broaden the design vision of BNCT nano-boron capture agents.

A feasibility study using an array of LaBr3(Ce) scintillation detectors as a Compton camera for prompt gamma imaging during BNCT

Boron Neutron Capture Therapy (BNCT) is a binary cancer therapy where a low energy neutron beam is incident upon a patient who has been administered a tumour-seeking 10B loaded compound. The neutron capture reaction on 10B results in the production of two short range particles, 7Li and 4He, that deposit all of their energies within the targeted cell. However, accurate, online dosimetry during BNCT is challenging as it requires knowledge of both the neutron fluence and 10B concentration in cells. An additional product in the neutron capture reaction on 10B is a 478 keV prompt gamma ray, and if the production vertices of these gamma rays could be imaged by an external camera, the density of the vertices could be used to infer the dose delivered to the patient. In this study, the feasibility of using an array of LaBr3 scintillators as a modified Compton camera for prompt gamma imaging during BNCT was investigated using Geant4 simulations. These simulations demonstrated that a phantom containing a 3 cm diameter region of 400 ppm 10B could be reconstructed using clinically relevant neutron fluences. This result opens up more possibilities for future research to improve dosimetry during BNCT.

Fluorinated BPA derivatives enhanced 10B delivery in tumors.

Boron neutron capture therapy (BNCT) is an emerging approach for treating malignant tumors with binary targeting. However, its clinical application has been hampered by insufficient 10B accumulation in tumors and low 10B concentration ratios of tumor-to-blood (T/B) and tumor-to-normal tissue (T/N). Herein, we developed fluorinated BPA derivatives with different fluorine groups as boron delivery agents for enabling sufficient 10B accumulation in tumors and enhancing T/B and T/N ratios. Our findings demonstrated that fluorinated BPA derivatives had good biological safety. Furthermore, fluorinated BPA derivatives showed improved 10B accumulation in tumors and enhanced T/B and T/N ratios compared to the clinical boron drug fructose-BPA (f-BPA). In particular, in B16-F10 tumor-bearing mice, fluorinated BPA derivatives met the requirements for clinical BNCT even at half of the clinical dose. Thus, fluorinated BPA derivatives are potentially effective boron delivery agents for clinical BNCT in melanoma.

Boron Neutron Capture Therapy: Microdosimetry at Different Boron Concentrations

This paper explores the role of microdosimetry in boron neutron capture therapy (BNCT), a cancer treatment involving the selective accumulation of boron-containing compounds in cancer cells, followed by neutron irradiation. Neutron interactions with 10B induces a nuclear reaction, releasing densely ionizing particles, specifically alpha particles and recoiling lithium-7 nuclei. These particles deposit their energy within a small tissue volume, potentially targeting cancer cells while sparing healthy tissue. The microscopic energy distribution, subject to significant fluctuations due to the short particle range, influences treatment efficacy. Microdosimetry, by studying this distribution, plays a crucial role in optimizing BNCT treatment planning. The methodology employs paired tissue equivalent proportional counters (TEPCs), one with cathode walls enriched with boron and the other without. Precise assessment of boron concentration is essential, as well as the ability to extrapolate results to the actual 10B concentration within the treatment region. The effective 10B concentrations within four boronated TEPCs, containing 10, 25, 70, and 100 ppm of 10B, have been determined. Results show variations of less than 3% from nominal values. Additionally, dose enhancement due to BNC interactions was measured and found to be proportional to the 10B concentration, with a proportionality factor of 7.7 × 10−3 per ppm of boron. Based on these findings, a robust procedure is presented for assessing the impact of BNCT in the treatment region, considering potential variations in boron content relative to the TEPC used.

From nuclear track characterization to machine learning based image classification in neutron autoradiography for boron neutron capture therapy.

Knowledge of the 10B microdistribution is of great relevance in BNCT studies. Since 10B concentration assesment through neutron autoradiography depends on the correct quantification of tracks in a nuclear track detector, image acquisition and processing conditions should be controlled and verified, in order to obtain accurate results to be applied in the frame of BNCT. With this aim, an image verification process was proposed, based on parameters extracted from the quantified nuclear tracks. Track characterization was performed by selecting a set of morphological and pixel-intensity uniformity parameters from the quantified objects (area, diameter, roundness, aspect ratio, heterogeneity and clumpiness). Their distributions were studied, leading to the observation of varying behaviours in images generated by different samples and acquisition conditions. The distributions corresponding to samples coming from the BNC reaction showed similar attributes in each analyzed parameter, proving to be robust to the experimental process, but sensitive to light and focus conditions. Considering those observations, a manual feature extraction was performed as a pre-processing step. A Support Vector Machine (SVM) and a fully dense Neural Network (NN) were optimized, trained, and tested. The final performance metrics were similar for both models: 93%-93% for the SVM, vs 94%-95% for the NN in accuracy and precision respectively. Based on the distribution of the predicted class probabilities, the latter had a better capacity to reject inadequate images, so the NN was selected to perform the image verification step prior to quantification. The trained NN was able to correctly classify the images regardless of their track density. The exhaustive characterization of the nuclear tracks provided new knowledge related to the autoradiographic images generation. The inclusion of machine learning in the analysis workflow proves to optimize the boron determination process and paves the way for further applications in the field of boron imaging.

Laser-Synthesized Elemental Boron Nanoparticles for Efficient Boron Neutron Capture Therapy

Boron neutron capture therapy (BNCT) is one of the most appealing radiotherapy modalities, whose localization can be further improved by the employment of boron-containing nanoformulations, but the fabrication of biologically friendly, water-dispersible nanoparticles (NPs) with high boron content and favorable physicochemical characteristics still presents a great challenge. Here, we explore the use of elemental boron (B) NPs (BNPs) fabricated using the methods of pulsed laser ablation in liquids as sensitizers of BNCT. Depending on the conditions of laser-ablative synthesis, the used NPs were amorphous (a-BNPs) or partially crystallized (pc-BNPs) with a mean size of 20 nm or 50 nm, respectively. Both types of BNPs were functionalized with polyethylene glycol polymer to improve colloidal stability and biocompatibility. The NPs did not initiate any toxicity effects up to concentrations of 500 µg/mL, based on the results of MTT and clonogenic assay tests. The cells with BNPs incubated at a 10B concentration of 40 µg/mL were then irradiated with a thermal neutron beam for 30 min. We found that the presence of BNPs led to a radical enhancement in cancer cell death, namely a drop in colony forming capacity of SW-620 cells down to 12.6% and 1.6% for a-BNPs and pc-BNPs, respectively, while the relevant colony-forming capacity for U87 cells dropped down to 17%. The effect of cell irradiation by neutron beam uniquely was negligible under these conditions. Finally, to estimate the dose and regimes of irradiation for future BNCT in vivo tests, we studied the biodistribution of boron under intratumoral administration of BNPs in immunodeficient SCID mice and recorded excellent retention of boron in tumors. The obtained data unambiguously evidenced the effect of a neutron therapy enhancement, which can be attributed to efficient BNP-mediated generation of α-particles.

The effects of BPA-BNCT on normal bone: determination of the CBE value in mice‡.

Boron neutron capture therapy (BNCT) with p-boronophenylalanine (BPA) is expected to have less effect on the decrease in normal bone strength than X-ray therapy. However, the compound biological effectiveness (CBE) value necessary to convert the boron neutron capture reaction (BNCR) dose into a bioequivalent X-ray dose has not been determined yet. The purpose of this study was to evaluate the influence of BNCT on normal bone in mice and to elucidate the CBE factor. We first searched the distribution of BPA in the normal bone of C3H/He mice and then measured the changes in bone strength after irradiation. The CBE value was determined when the decrease in bone strength was set as an index of the BNCT effect. The 10B concentrations in the tibia after subcutaneous injection of 125, 250 and 500mg/kg BPA were measured by prompt gamma-ray spectroscopy and inductively coupled plasma (ICP)-atomic emission spectrometry. The 10B mapping in the tibia was examined by alpha-track autoradiography and laser ablation-ICP-mass spectrometry. The 10B concentration increased dose-dependently; moreover, the concentrations were maintained until 120min after BPA administration. The administered 10B in the tibia was abundantly accumulated in the growth cartilage, trabecular bone and bone marrow. The bone strength was analyzed by a three-point bending test 12weeks after irradiation. The bending strength of the tibia decreased dose-dependently after the irradiation of X-ray, neutron and BNCR. The CBE factor was obtained as 2.27 by comparing these dose-effect curves; the value determined in this study will enable an accurate dosimetry of normal bone.

Monte Carlo Simulation Study on the Optimal Neutron Energy and Boron Concentration for SARS-COV-2 Inactivation through BNCT

Researchers have been exploring various radiation therapies to treat COVID-19 patients ranging from mild to severe. One technique that has shown promise is Boron Neutron Capture Therapy (BNCT). This therapy involves administering of 10B isotope to the targeted area, which is then exposed to chargeless neutrons. These neutrons can be absorbed by areas with high concentrations of 10B. When the neutrons react with the 10B (10B + n?7Li + 4He reaction), it results in the transfer of highly ionizing energy, causing confined lethality and destroying the targeted area. In this study, we used the Particle and Heavy Ion Transport Code System simulation to evaluate whether Boron Neutron Capture Therapy could be effective as an anti-viral therapy. The study involves creating a model of the SAR-COV-2 target phantom's geometry and defining its chemical composition to collect data. It was found out that when tested at different neutron energies and concentrations (30 ppm, 50 ppm, and 100 ppm), a sufficient amount of dose to cause biological damage to the Sars-CoV-2 enveloped protein could be achieved with 30 ppm boron concentration and a neutron energy of 1.0x10-10 MeV.

An Integrated Monte Carlo Model for Heterogeneous Glioblastoma Treated with Boron Neutron Capture Therapy.

Glioblastomas (GBMs) are notorious for their aggressive features, e.g., intrinsic radioresistance, extensive heterogeneity, hypoxia, and highly infiltrative behaviours. The prognosis has remained poor despite recent advances in systemic and modern X-ray radiotherapy. Boron neutron capture therapy (BNCT) represents an alternative radiotherapy technique for GBM. Previously, a Geant4 BNCT modelling framework was developed for a simplified model of GBM. The current work expands on the previous model by applying a more realistic in silico GBM model with heterogeneous radiosensitivity and anisotropic microscopic extensions (ME). Each cell within the GBM model was assigned an α/β value associated with different GBM cell lines and a 10B concentration. Dosimetry matrices corresponding to various MEs were calculated and combined to evaluate cell survival fractions (SF) using clinical target volume (CTV) margins of 2.0 & 2.5 cm. SFs for the BNCT simulation were compared with external X-ray radiotherapy (EBRT) SFs. The SFs within the beam region decreased by more than two times compared to EBRT. It was demonstrated that BNCT results in markedly reduced SFs for both CTV margins compared to EBRT. However, the SF reduction as a result of the CTV margin extension using BNCT was significantly lower than using X-ray EBRT for one MEP distribution, while it remained similar for the other two MEP models. Although the efficiency of BNCT in terms of cell kill is superior to EBRT, the extension of the CTV margin by 0.5 cm may not increase the BNCT treatment outcome significantly.

The impact of TP53 status of tumor cells including the type and the concentration of administered 10B delivery agents on compound biological effectiveness in boron neutron capture therapy.

Human head and neck squamous cell carcinoma cells transfected with mutant TP53 (SAS/mp53) or neo vector (SAS/neo) were inoculated subcutaneously into left hind legs of nude mice. After the subcutaneous administration of a 10B-carrier, boronophenylalanine-10B (BPA) or sodium mercaptododecaborate-10B (BSH), at two separate concentrations, the 10B concentrations in tumors were measured using γ-ray spectrometry. The tumor-bearing mice received 5-bromo-2'-deoxyuridine (BrdU) continuously to label all intratumor proliferating (P) tumor cells, then were administered with BPA or BSH. Subsequently, the tumors were irradiated with reactor neutron beams during the time of which 10B concentrations were kept at levels similar to each other. Following irradiation, cells from some tumors were isolated and incubated with a cytokinesis blocker. The responses of BrdU-unlabeled quiescent (Q) and total (= P + Q) tumor cells were assessed based on the frequencies of micronucleation using immunofluorescence staining for BrdU. In both SAS/neo and SAS/mp53 tumors, the compound biological effectiveness (CBE) values were higher in Q cells and in the use of BPA than total cells and BSH, respectively. The higher the administered concentrations were, the smaller the CBE values became, with a clearer tendency in SAS/neo tumors and the use of BPA than in SAS/mp53 tumors and BSH, respectively. The values for BPA that delivers into solid tumors more dependently on uptake capacity of tumor cells than BSH became more alterable. Tumor micro-environmental heterogeneity might partially influence on the CBE value. The CBE value can be regarded as one of the indices showing the level of intratumor heterogeneity.

Reporting Dose in Boron Neutron Capture Therapy.

Reporting needs uniformity in definitions and terminology. This is crucial in order to be able to compare and aggregate clinical outcomes data across clinical trials. For decades, there is no standard for reporting dose in boron neutron capture therapy (BNCT). Multiple efforts were made for a common language reporting BNCT, mostly suggesting to report at relevant points the different dose components separately. Although this was accepted by some but not all clinicians, the situation remains an unsatisfactory and cumbersome reporting system, leading to confusion. Another suggestion is made here by proposing not to report the results of calculations that use a site-specific model with certain assumptions, but to report the input parameters needed for such calculations regardless of the model used. This will be mainly the thermal neutron fluence integrated over the irradiation time T and the average 10B concentration integrated over T.

Clinical Viability of Boron Neutron Capture Therapy for Personalized Radiation Treatment.

Simple SummaryUsually, for dose planning in radiotherapy, the tumor is delimited as a volume on the image of the patient together with other clinical considerations based on populational evidence. However, the same prescription dose can provide different results, depending on the patient. Unfortunately, the biological aspects of the tumor are hardly considered in dose planning. Boron Neutron Capture Radiotherapy enables targeted treatment by incorporating boron-10 at the cellular level and irradiating with neutrons of a certain energy so that they produce nuclear reactions locally and almost exclusively damage the tumor cell. This technique is not new, but modern neutron generators and more efficient boron carriers have reactivated the clinical interest of this technique in the pursuit of more precise treatments. In this work, we review the latest technological facilities and future possibilities for the clinical implementation of BNCT and for turning it into a personalized therapy.Boron Neutron Capture Therapy (BNCT) is a promising binary disease-targeted therapy, as neutrons preferentially kill cells labeled with boron (10B), which makes it a precision medicine treatment modality that provides a therapeutic effect exclusively on patient-specific tumor spread. Contrary to what is usual in radiotherapy, BNCT proposes cell-tailored treatment planning rather than to the tumor mass. The success of BNCT depends mainly on the sufficient spatial biodistribution of 10B located around or within neoplastic cells to produce a high-dose gradient between the tumor and healthy tissue. However, it is not yet possible to precisely determine the concentration of 10B in a specific tissue in real-time using non-invasive methods. Critical issues remain to be resolved if BNCT is to become a valuable, minimally invasive, and efficient treatment. In addition, functional imaging technologies, such as PET, can be applied to determine biological information that can be used for the combined-modality radiotherapy protocol for each specific patient. Regardless, not only imaging methods but also proteomics and gene expression methods will facilitate BNCT becoming a modality of personalized medicine. This work provides an overview of the fundamental principles, recent advances, and future directions of BNCT as cell-targeted cancer therapy for personalized radiation treatment.

The Development of Boron Analysis and Imaging in Boron Neutron Capture Therapy (BNCT).

Boron neutron capture therapy (BNCT) is a selective biological targeted nuclide technique for cancer therapy. It has the following attractive features: good targeting, high effectiveness, and causes slight damage to surrounding healthy tissue compared with other traditional methods. It has been considered as one of the promising methods for the treatment of various cancers. Measuring 10B concentrations is vital for BNCT. However, the existing technology and equipment cannot satisfy the real-time and accurate measurement requirements, and more efficient methods are in demand. The development of methods and imaging applied in BNCT to help measure boron concentration is described in this review.

Feasibility of Prompt Gamma Ray Detection and Imaging Using CdTe Detectors for BNCT ― Monte Carlo Study

Boron neutron capture therapy (BNCT) has experienced a renaissance in recent years, due to the availability of accelerator-based neutron sources and more effective delivery vehicles of boron-10 (10B). For successful BNCT, 10B concentration and distribution in the tumor (as well as in the critical organs) must be determined non-invasively prior to BNCT treatments. While conventional nuclear imaging (e.g., PET/SPECT), in conjunction with radiolabeled 10B, may serve for this purpose, another approach, based on the detection of prompt gamma (PG) rays from the BNC reaction, appears to be more attractive, most notably because it can be implemented within the BNCT setup without radiolabeling of 10B. The detectability of PG rays (478 keV) from the BNC reaction has been shown experimentally within the context of BNCT utilizing energy-resolving solid-state detectors. However, the feasibility of this approach under the clinically relevant conditions is currently unknown. Thus, the present work investigated this feasibility by performing Monte Carlo (MC) simulations using the simulation toolkit.MC models of various phantom cases were created to simulate epithermal neutron beam irradiation relevant to accelerator-based BNCT (a-BNCT). For benchmarking and future experimental verification, the phantom geometry (20 cm-diameter/24 cm-height cylinder) and material (PMMA) were chosen based on a published experimental study. The phantom had 3 cm-diameter/3.8 cm-height cylindrical inserts (located at 5 cm depth along the long-axis of the phantom) that contained 10B solution at different concentrations ranging from 1 - 30,000 parts-per-million (ppm). For detection of PG rays, a 23.1 cm-diameter ring detector consisting of 120 cadmium telluride (CdTe) crystals was modeled. CdTe was chosen because of its high photon counting efficiency and energy resolution. Each CdTe detector crystal (5 × 5 × 1 mm3) contained an inherent 0.1mm-thick beryllium window and a novel/custom thermal neutron filter made of gadolinium. Two billion incident neutron histories were used during each MC simulation. The detected PG ray signals were used to test both direct mapping and CT techniques for quantitative imaging.The current MC simulations showed PG ray signals from the10B-loaded tumor-mimicking cylindrical insert were above the background noise (with a 95% confidence level), down to the clinically achievable tumor 10B concentration of 30 ppm. The custom thermal neutron filter was effective in suppressing the inherent background from CdTe detectors.This MC study demonstrated the detectability of PG rays from the BNC reaction using CdTe detectors under the conditions closely mimicking realistic a-BNCT scenarios. It also showed that clinically acceptable quantitative imaging of 10B distribution could be performed utilizing the PG ray signals from the BNC reaction.H. Moktan: None. C. Lee: None. S. Cho: Research Grant; TAE Life Sciences.

Development of an Imaging Technique for Boron Neutron Capture Therapy.

The development of 4-10B-borono-2-18F-fluoro-L-phenylalanine (18FBPA) for use in positron emission tomography (PET) has contributed to the progress of boron neutron capture therapy (BNCT). 18FBPA has shown similar pharmacokinetics and distribution to 4-10B-borono-L-phenylalanine (BPA) under various conditions in many animal studies. 18FBPA PET is useful for treatment indication. A higher 18FBPA accumulation ratio of the tumor to the surrounding normal tissue (T/N ratio) indicates that a superior treatment effect is expected. In clinical settings, a T/N ratio of higher than 2.5 or 3 is often used for patient selection. Moreover, 18FBPA PET is useful for predicting the 10B concentration delivered to the tumor and surrounding normal tissues, enabling high-precision treatment planning. Precise dose prediction using 18FBPA PET data has greatly improved the treatment accuracy of BNCT. However, the methodology used for the data analysis of 18FBPA PET findings varies; thus, data should be evaluated using a consistent methodology so as to be more reliable. In addition to PET applications, the development of 18FBPA as a contrast agent for magnetic resonance imaging that combines gadolinium and 10B is also in progress.

ASSESSMENT OF THE EFFECT OF BORON NEUTRON CAPTURE THERAPY ON TUMOR CELL LINES AND PRIMARY EMBRYONIC CELL CULTURE

Introduction. Boron neutron capture therapy (bnct) is a promising method for treating tumors, in particular, infiltrative malignant tumors, due to the selective destruction of tumor cells without damaging the surrounding normal tissues. This type of therapy is based on nuclear reaction of neutron capture by stable 10b isotope. For the successful implementation of bnct, boron delivery drugs that must be selectively accumulated in malignant cells in a sufficient amount, and a neutron source with the energy required for the neutron capture reaction are needed. At the budker institute of nuclear physics, the accelerator-based neutron source was designed with flux parameters allowing studies on bnct to be conducted.Objective: to assess the effect of bnct on tumor and normal cell lines using borphenylalanine (bpa), borcaptate (bsh) and liposomal borcaptat as boron delivery drugs.Materials and methods. Human cell cultures: glioblastoma (u87), colorectal human adenocarcinoma (sw-620), human melanoma (sk-mel28) and primary embryonic cell lines were irradiated with a neutron flux at the presence of bpa, bsh and liposomal bsh with a concentration of 10b 40 μg/ml. The short-term cytotoxic effect of irradiation was evaluated using trypan blue. Cell survival 96 hours after irradiation was determined using mtt test, and survival fraction was evaluated using the clonogenic test.Results. Early cytotoxic effects of irradiation were not observed for all 4 cell lines. According to mtt and clonogenic tests, the most pronounced effect of bnct was noticed for sw-620 and u87 lines, regardless of boron delivery drug used. For sk-mel28 line, the best effect was achieved after irradiation with liposomal borocaptate. For the primary transplanted embryonic line, high toxicity was revealed when bnct was performed with borphenylalanine and borcaptate.Conclusion. The data obtained indicate that the accelerator-based bnct using boron delivery drugs, such as borphenylalanine, borcaptate and liposomal borcaptat, has a positive effect on tumor lines of glioblastoma, colorectal adenocarcinoma and melanoma.

Theranostics in Boron Neutron Capture Therapy

Boron neutron capture therapy (BNCT) has the potential to specifically destroy tumor cells without damaging the tissues infiltrated by the tumor. BNCT is a binary treatment method based on the combination of two agents that have no effect when applied individually: 10B and thermal neutrons. Exclusively, the combination of both produces an effect, whose extent depends on the amount of 10B in the tumor but also on the organs at risk. It is not yet possible to determine the 10B concentration in a specific tissue using non-invasive methods. At present, it is only possible to measure the 10B concentration in blood and to estimate the boron concentration in tissues based on the assumption that there is a fixed uptake of 10B from the blood into tissues. On this imprecise assumption, BNCT can hardly be developed further. A therapeutic approach, combining the boron carrier for therapeutic purposes with an imaging tool, might allow us to determine the 10B concentration in a specific tissue using a non-invasive method. This review provides an overview of the current clinical protocols and preclinical experiments and results on how innovative drug development for boron delivery systems can also incorporate concurrent imaging. The last section focuses on the importance of proteomics for further optimization of BNCT, a highly precise and personalized therapeutic approach.

Boron uptake and distribution by oilseed rape (Brassica napus L.) as affected by different nitrogen forms under low and high boron supply

Ammonium (NH4+) and nitrate (NO3−) conversely alter pH of the rooting medium, and thus differentially affect the equilibrium between boric acid and borate in soil solution. This can alter boron (B) uptake by plants, which is passive under high, but facilitated (boric acid) or active (borate) under low B supply. Therefore, the effect of NH4+ and NO3− forms was investigated on the growth, 10B uptake rate and accumulation, and expression of B transporters in Brassica napus grown with low (1 μM) or high (100 μM) 10B for five days in the nutrient solution. At the low 10B level, NO3−-fed plants had the same specific 10B uptake rate, 10B accumulation and xylem 10B concentration as NH4NO3-fed plants but these attributes were reduced at the high 10B level. BnaBOR1;2 and BnaNIP5;1 were upregulated in roots of NO3-fed plants at low 10B supply. NH4+-fed plants had substantially lower dry matters; due to nutrient solution acidification (2.0 units)-induced deficiency of nitrogen, potassium, magnesium, and iron in plant shoots. Reduced transpiration rates resulted in lower 10B uptake rate and accumulation in the roots and shoots of NH4+-fed plants. BnaNIP5;1 in roots, while both BnaBOR1;2 and BnaNIP5;1 in shoots were upregulated in NH4+-fed plants at low 10B level. Collectively, NH4+-induced acidity and consequent lowering of 10B uptake induced the upregulation of B transport mechanisms, even at marginal 10B concentrations, while NO3−-induced alkalinization resulted in altered B distribution between roots and shoots due to restricted B transport, especially at higher 10B supply.

Improving the spatial resolution of a pixelated LaBr3(Ce) scintillator coupled with a multi-pixel photon counter array for boron neutron capture therapy

Fundamental preclinical research with mice to improve boron neutron capture therapy requires a prompt gamma-ray imaging detector that can chart the real-time accumulation of 10B in tumors. This study aimed to improve the spatial resolution of our previous detector, which was based on a slab-shape LaBr3(Ce) scintillator, by changing to a pixelated 8 × 8 array scintillator.The difference between the scintillation-light detection processes, such as Compton scattering and the photoelectron effect, affects energy resolution. This was experimentally revealed and evaluated with Monte Carlo simulations. The events caused by Compton scattering were eliminated, and our detector obtained the desired energy resolution for 511 keV gamma rays at 5.0 ± 0.4 %. The spatial resolution was evaluated using collimated gamma rays and was found to be better than that of the previous system because the scintillation light did not spread over the pixelated scintillator. As a result, the proposed detection system had the energy resolution to discriminate between 478- and 511-keV gamma rays to obtain the 10B concentration. The lateral and vertical spatial resolutions FWHM of the improved system were 5.9 mm and 5.2 mm, respectively, which were better than the value of 8.0 mm provided by the previous system to visualize the two-dimensional distribution in real time.

Determination of the long-lived 10Be in construction materials of nuclear power plants using photoactivation method

The problem of handling nuclear power plant irradiated structural materials holds one of the central places in the nuclear power industry. High toxic 10Be with a half-life of T1/2 = 1.6 × 106 years is discovered in NPP structural materials after reactor operating. 10Be decays through only electrons' emission. Pure beta emitters are extremely difficult to determine in irradiated structural materials and radioactive waste. We proposed a photoactivation approach for determining the 10Be activity in NPP samples. The proposed method involves determining 9Be and 10B concentrations and subsequent recalculation of 10Be activity formed in 9Be(n, γ)10Be and 10B(n, p)10Be reactions. The amount of 9Be and 10B is determined by samples' photoactivation using an electron accelerator and 9Be(γ, 2n)7Be-, 10B(γ, p2n)7Be-reactions. These reactions' experimental yields were measured for 20, 40, and 55 MeV boundary energies of the bremsstrahlung beam. The proposed technique was tested on samples of ChNPP 2nd unit irradiated structural materials. The technique's calculated error is about 15–20%; the sensitivity is 1 Bq × g−1.