Capture Reaction Research Articles

Increased cell killing effect in neutron capture enhanced proton beam therapy

AbstractThermal neutrons generated in the body during proton beam therapy (PBT) can be used to cause boron neutron capture reactions and have recently been proposed as neutron capture enhanced PBT (NCEPBT). However, the cell killing effect of NCEPBT remains underexplored. Here, we show an increase in the cell killing effect of NCEPBT. Using Monte Carlo simulations, we showed that neutrons generated by proton beam irradiation are uniformly spread on tissue culture plates. Human salivary gland tumor cell line (HSG), human osteosarcoma cell line (MG63), human tongue squamous cell carcinoma cell line (SAS), and human malignant melanoma cell line (G-361) were irradiated with X-rays, proton beams, and proton beams with 10B-enriched boronophenylalanine (boron concentration of 20 and 80 ppm). The relative biological effectiveness (RBE) values of proton beams alone, proton beams with 20 ppm boron, and proton beams with 80 ppm boron for HSG, MG63, SAS, and G-361 were 1.02, 1.07, and 1.23; 1.01, 1.08, and 1.44; 1.05, 1.09, and 1.46; and 1.04, 1.13, and 1.63, respectively. NCEPBT with high boron concentration showed high RBE and a high sensitizing effect. Our results confirm an increase in the cell killing effect of NCEPBT, should aid in its clinical use, and warrant its further investigation.

TMET-13. SPATIAL METABOLOMIC CHANGES OF NUCLEOTIDE IN THE BRAINS OF ORTHOTOPIC MOUSE GLIOMA MODEL AFTER BORON NEUTRON CAPTURE THERAPY (BNCT)

Abstract Glioblastoma is the most lethal primary brain tumor. Boron Neutron Capture Therapy (BNCT) is a tumor-selective particle radiation therapy, in which high-LET α-particles and recoil 7Li are produced by the capture reaction between 10B and thermal neutrons and it has extended the prognosis of glioblastomas [Kawabata S, et al., Neuro-Oncology Advances 3(1), 1–9, 2021]. Augmented synthesis and use of nucleotide triphosphates is critical and universal metabolic dependency of tumor cells [Mullen, N.J., Singh, P.K. Nat Rev Cancer 23, 275–294 (2023)]. However, the effects of BNCT on metabolism of purine and pyrimidine in brain tumors and the surrounding normal brain are unknown. We spatially investigated metabolomic change in brains of orthotopic mouse glioma model, before and 2, 7, and 14 days after BNCT using mass spectrometry imaging (MSI). By separating tumor and non-tumor areas and performing Partial Least Squares Regression calculations, we have successfully visualized tumor-specific metabolites including adenine (ATP, ADP) and uridine (UTP, UDP-glucose, UDP-GlcNAc) with MSI. Of note, the signal of top-scored tumor specific metabolite, UDP-GlcNAc dramatically decreased and disappeared as the tumor regressed. Furthermore, the signal of ADP which was supposed to be released from tumor, colocalized with invading tumors along with corpus callosum. The value of adenylate energy charge, ([ATP]+0.5[ADP]/[ATP]+[ADP]+[AMP]) in the surrounding normal brain of the untreated tumor-bearing mouse increased up to 0.37 and decreased gradually down to 0.32 with BNCT, approaching to the value of normal control mouse brain, 0.27. These metabolomic changes reflected the tumor-killing effect and restoration of energy charge of surrounding normal brain by BNCT and have potential significance for development of biomarker or diagnosis.

Estimation of joint kinetics during manual material handling using inertial motion capture: a follow-up study.

Musculoskeletal models based on inertial motion capture and ground reaction force (GRF) prediction hold great potential for field-based risk assessment of manual material handling. However, previous evaluations have identified inaccuracies in the methodology?s estimation of spinal forces, while the accuracy of other key outcome variables is currently unclear. This study evaluated knee, shoulder, and L5-S1 joint reaction forces (JRFs) derived from a musculoskeletal model based on inertial motion capture and GRF prediction against a model based on simultaneously collected optical motion capture and force plate measurements. Data from 19 healthy subjects performing lifts with various horizontal locations, deposit heights and asymmetry angles were analyzed, and the consistency and absolute agreement of the model estimates statistically compared. Despite varying levels of agreement across tasks and variables, considerable absolute differences were identified for the L5-S1 axial compression (RMSE = 63.0-94.2%BW) and anteroposterior shear forces (RMSE = 40.9-80.6%BW) as well as the bilateral knee JRFs (RMSE = 78.9-117%BW). Glenohumeral JRFs and vertical GRFs exhibited the highest overall consistency (r = 0.33-0.91, median 0.78) and absolute agreement (RMSE = 7.63-34.9%BW), while the L5-S1 axial compression forces also showed decent consistency (r = 0.04-0.89, median 0.80). The findings generally align with prior evaluations, indicating persistent challenges with the accuracy of key outcome variables. While the modelling framework shows promise, further development of the methodology is encouraged to enhance its applicability in ergonomic evaluations.

Design and Construction of Experimental System for Validation of a New Image Reconstruction Technique with Limited-view-angle Projection Data for BNCT-SPECT

Abstract. Boron Neutron Capture Therapy (BNCT) is expected to be a promising radiation therapy for cancer, and research on various issues associated with it is still in progress. One of the unsolved issues is the construction of a system for observing the effect of the treatment (local boron dose) in real time under high-background circumstances. Thus, we set out to establish a method for measuring gamma-rays emitted promptly from the body following the boron neutron capture reaction and reconstructing images in a SPECT-like manner. We call this method BNCT-SPECT. We have been developing a new image reconstruction method based on Bayesian estimation for the BNCT-SPECT method. In the present study, the aims were to design and construct an experimental system capable of validating BNCT-SPECT and its image reconstruction method and to confirm BNCT-SPECTs performance. The crucial takeaway from this study is that we should consider the use of extremely high background radiation during BNCT. For the validation of BNCT-SPECT, we attempted to reproduce these conditions, despite this being quite challenging. We first constructed an experimental system capable of reproducing such conditions. Theoretical investigation was carried out to facilitate the design of the system using the Monte Carlo transport calculation code MCNP. Finally, we performed experiments with some standard gamma-ray sources to complete the system.

Validity analysis of γ-ray strength function models for radiative capture reactions of heavy nuclei

Accurate simulation of radiative capture reactions (RCRs) requires precise modeling of [Formula: see text]-ray strength functions (GSF). Various GSF models exist but need normalization based on experimental total radiative width (TRW) data. This study found that current normalization methods fail for neutron-induced RCRs in [Formula: see text]U and [Formula: see text]Th nuclei. In this regard, re-normalization values are proposed in order to improve model consistency at low energies. The standard Lorentzian (SLO) model fits experimental data best with minimal normalization.

Boron Agent Delivery Platforms Based on Natural Products for Boron Neutron Capture Therapy.

Boron neutron capture therapy (BNCT) is one of the most promising modalities for cancer treatment due to its minimal invasiveness. Although two types of boron agents are clinically used, several issues persist in their delivery, including poor water solubility, instability in aqueous media, selectivity toward cancer cells, accumulation in cancer cells, retention time in tumor tissue, and efficiency in achieving the boron neutron capture reaction. Addressing these challenges, numerous groups have explored various boron agents to enhance the therapeutic benefits of BNCT. This review summarizes delivery platforms based on natural products for BNCT.

Metal Oxalates as a CO2 Solid State Reservoir: The Carbon Capture Reaction

Metal Oxalates as a CO2 Solid State Reservoir: The Carbon Capture Reaction

Mechanistic Insights into the Reactivity and Activation Barrier Origins for CO2 Capture by Heavy Group-14 Imine Analogues.

Using M06-2X-D3/def2-TZVP, the [2 + 2] cycloaddition reactions of carbon dioxide with the heavy imine analogues G14=N-Rea (G14 = Group 14 element) were investigated. The theoretical evidence reveals that the nature of the doubly bonded G14=N moiety in heavy imine analogues, G14=N-Rea (L1L2G14=N-L3), is characterized by the electron-sharing interaction between triplet L1L2G14 and triplet N-L3 fragments. Based on our theoretical studies, except for the carbon-based imine, all four heavy imine analogues with Si=N, Ge=N, Sn=N, and Pb=N groups can easily engage in [2 + 2] cycloaddition reactions with CO2. Energy decomposition analysis-natural orbitals for chemical valence analyses and the FMO theory strongly suggest that in the CO2 capture reaction by heavy imine analogues G14=N-Rea, the primary bonding interaction is the occupied p-π orbital (G14=N-Rea) → vacant p-π* orbital (CO2) interaction, instead of the empty p-π* orbital (G14=N-Rea) ← filled p-π orbital (CO2) interaction. The activation barrier of the CO2 capture reactions by G14=N-Rea molecules is primarily determined by the deformation energy of CO2. Shaik's valence bond state correlation diagram model, used to rationalize the computed results, indicates that the singlet-triplet energy splitting of G14=N-Rea is a key factor in determining the reaction barrier for the current CO2 capture reactions.

Preliminary study of a compact epithermal neutron absolute flux intensity measurement system for real-time in-vivo dose monitoring in boron neutron capture therapy

Boron neutron capture therapy (BNCT) is a radiotherapy technology that selectively kills tumor cells via the 10B(n, α)7Li reactions. Epithermal neutrons (0.5 eV–10 keV) are emitted and converted into thermal neutrons, which have a larger neutron capture reaction cross-section, by slowing down in the human body before reaching the tumor. Recently, the development of an epithermal neutron absolute flux intensity measurement technique has become crucial for real-time in-vivo dose monitoring in BNCT. In this study, a concept for a measurement system consisting of multiple compact scintillator with optical fibers detectors covered with neutron absorbers of various thicknesses is proposed. The designed system achieves a consistent response to epithermal neutrons with a theoretical coefficient of variation not higher than 5% for both LiCAF and EJ-254 scintillators. The theoretical feasibility of the proposed measurement system was investigated by an irradiation experiment carried out at the heavy water neutron irradiation facility at the Kyoto University Reactor. The experimental results indicated that further improvement and refinement are necessary to meet the high accuracy and precision required for real-time dose monitoring in clinical applications.

Impact of nuclear level density and γ-ray strength function in (n,γ) and Maxwellian-averaged cross-section of 69Zn nucleus

The present paper highlights the impact of nuclear level density (NLD) and γ-ray strength function (γ-SF) on (n,γ) and Maxwellian-averaged cross-section of 69Zn nucleus. At first, the existing NLD and γ-SF models (in TALYS statistical model code) have been utilized to understand the role of NLD and γ-SF in neutron capture reaction cross-section. It is seen that most of the combinations of existing NLDs and γ-SFs (phenomenological and/or microscopic) cannot explain the experimental data. Therefore, the microscopic exact pairing plus independent particle model (EP+IPM) and exact pairing plus phonon damping model (EP+PDM) have been carried out to calculate the NLD and γ-SF of 69Zn nucleus, respectively, by employing the exact treatment of thermal pairing. It is seen that microscopic EP+IPM NLD and EP+PDM γ-SF explain the experimental data better than all other combinations available in TALYS-1.95, indicating the impact of the exact treatment of thermal pairing correlation. In addition, the inclusion of an upbend (UB) structure in γ-SF further improves the comparison with the experimental data in the low energy region (∼0.01–0.15 MeV), indicating the possibility of having an UB structure in γ-SF of 69Zn. The 68Zn(n,γ)69Zn reaction cross-section obtained by utilizing the EP+IPM NLD and EP+PDM γ-SF including UB structure is then used to predict the Maxwellian-averaged cross-sections, and the obtained results show reasonable agreement with all the available experimental data taken from the Karlsruhe Astrophysical Database of Nucleosynthesis in Stars. The present results reflect the impact of microscopic NLD and γ-SF on the precise description and/or prediction of the astrophysical reaction cross-section.

A study of the fine-structure constant dependence of radiative capture in Halo-EFT

We study the fine structure constant dependence of the rates of some selected radiative capture reactions within the framework of so-called Halo Effective Field Theory in order to assess the adequacy of some assumptions made on the Coulomb penetrability. We find that this dependence deviates from that implied by a parameterization of the cross sections of this effect via a simple penetration factor. Some features of this fine-structure dependence are discussed, in particular its potential impact on the abundances of the light elements in primordial nucleosynthesis.

Research on CO2 capture performance and reaction mechanism using a novel low energy consumption and high cyclic performance absorbent for onboard application

High desorption energy consumption and low cyclic loading are critical issues limiting the application of onboard carbon capture (OCC) systems. In this study, a tetraethylenepentamine (TEPA) and 2–amino–2–methyl–1–propanol (AMP) mixed amine solvent with low desorption energy consumption and high CO2 cyclic loading, suitable for the operational environment of OCC systems, has been proposed. Detailed research was conducted on the capture performance and mechanism of the TEPA + AMP mixed amine solvent. The 0.25M TEPA+0.75M AMP mixed amine solvent exhibited the best performance, with an 86.5% increase in CO2 loading, a 214% increase in single–cycle CO2 loading, a 236% increase in CO2 loading after four cycles compared to monoethanolamine (MEA), and a 20.76% reduction in desorption energy consumption. In addition, to address the challenge of applying polyamine mixed solutions in the simulation studies of OCC systems, the capture mechanism was analyzed using density functional theory (DFT) calculations and nuclear magnetic resonance (NMR) characterization. The results indicated that increasing AMP promoted HCO3– formation in the TEPA + AMP mixed amine solvent. Since HCO3– decomposed more easily than carbamate, it reduced desorption energy consumption. However, an excess of AMP inhibited the absorption rate of TEPA, affecting the absorption capacity. Increasing the concentration of TEPA enhanced the amine concentration in the absorbent and improved the absorption performance. Nevertheless, excessive TEPA caused AMP to participate only in deprotonation reactions, which was not conducive to reducing desorption energy consumption.

The production and separation of 161Tb with high specific activity at the University of Utah

Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t1/2 = 6.95 days), which undergoes beta emission and shares similar decay properties as 177Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission, 161Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, G64160dn,γG64161d→3.66min,β−T65161b, from 160Gd targets. However, a key challenge in utilizing 161Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added 161Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: 1.356×1012n∙cm−2∙s−1) like the University of Utah TRIGA Reactor, using enriched 160Gd2O3 targets (1.5 ± 0.3 μCi of 161Tb per mg of 160Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation, 161Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5–0.75 M HNO3) methods. This resulted in high apparent molar activities of [161Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity 161Tb relevant for potential future preclinical applications.

A novel framework for the economic and sustainability assessment of carbon capture and utilization technologies

This study presents a novel framework for assessing early-stage carbon capture and utilization (CCU) reactions. The introduced greenhouse gas abatement, sustainability, and economics framework (GASEF) assesses commercial viability by simultaneously analyzing a CCU technology's CO2 fixation potential with its economic potential. The developed framework combines a previously published CO2Fix parameter and the metric for inspecting reactants and sales (MISR) to estimate CO2 fixation and economic potentials. Both metrics can be estimated using limited information such as temperature, pressure, conversion, molecular weights, the heat of reaction, and the prices of the reactants and products of the CCU reaction. Results from this novel framework are demonstrated via case studies of notable CCU technologies, such as Dry Reforming of Methane and CO2 hydrogenation to methanol processes. Furthermore, the possible implications of providing CO2 subsidies for CCU processes for the gross CO2 input into these processes versus providing CO2 subsidies for the net CO2 fixation of the process is evaluated. In particular, the GASEF assessment on the DRM process showcased a potential for commercial viability even when the technology implementation requires additional investment of 0.1 $/kgCO2 (pertaining to low-concentration CO2 streams) due to carbon capture and sequestration efforts to achieve net-zero emissions. In the case of CO2 hydrogenation to methanol process, the GASEF assessment showcased the potential for commercial viability only at low CO2 credit (0.05 $/kgCO2); however, at values higher than this, the process becomes tenuous. These case studies provide a comprehensive demonstration of the use of the GASEF as a versatile tool to support rapid economics and sustainability evaluation of the new CCU technologies.

Candidate-nuclei for observation of a bound dineutron. Part II: The (n,2n + n) and (γ,2n) nuclear reactions

This is a second part of a survey for stable isotopes in the mass range 90 < A < 210, to find candidates showing the bound dineutron nuclear reaction output channel after irradiation with neutrons or photons. To this end, the neutron capture reaction cross sections were calculated in the (0 - 30) MeV energy range with the TALYS-2.0 code for nuclei in the outgoing channel, which are expected to host bound dineutrons. This study was performed to find appropriate candidates to observe bound dineutron decay meeting the criteria based on the (n, γ) resonance cross section analysis. This study opens up a new direction in dineutron research with the (n, n2+n) and (γ, n2) nuclear reactions.

Radiative neutron capture reaction rates for stellar nucleosynthesis

AbstractThere is a high demand for nuclear data in multidisciplinary subject like nuclear astrophysics. The two areas of nuclear physics which are most clearly related to one another are stellar evolution and nucleosynthesis. The necessity for nuclear data for astrophysical applications puts experimental methods as well as reliability and predicative ability of current nuclear models to the test. Despite recent, considerable advances, there are still significant issues and mysteries. Only a few characteristics of nuclear astrophysics are covered in the current work which include $$^{52}$$ 52 Fe(n,$$\gamma $$ γ )$$^{53}$$ 53 Fe, $$^{53}$$ 53 Fe(n,$$\gamma $$ γ )$$^{54}$$ 54 Fe, $$^{54}$$ 54 Fe(n,$$\gamma $$ γ )$$^{55}$$ 55 Fe, $$^{55}$$ 55 Fe(n,$$\gamma $$ γ )$$^{56}$$ 56 Fe, $$^{56}$$ 56 Fe(n,$$\gamma $$ γ )$$^{57}$$ 57 Fe, $$^{57}$$ 57 Fe(n,$$\gamma $$ γ )$$^{58}$$ 58 Fe and $$^{58}$$ 58 Fe(n,$$\gamma $$ γ )$$^{59}$$ 59 Fe reactions which are important in stellar nucleosynthesis. The reaction rates are calculated using nuclear statistical model. These rates are subsequently fitted to polynomials of temperature T$$_9$$ 9 in order to facilitate calculations for stellar nucleosynthesis.

Regiodivergent Gold-Catalyzed Rearrangement-Addition Reactions of Sulfenylated Propargylic Carboxylates with Indoles.

Sulfenylated propargylic carboxylates were introduced to investigate the influence of sulfur substitution in gold-catalyzed alkyne activation pathways. Regiodivergent gold-catalyzed rearrangement and indole capture reactions proceed under mild conditions to give functionalized indole products bearing sulfenylated (Z)-enol carboxylate motifs. Pathways involving both 1,2- and 1,3-carboxylate migrations are achieved selectively, with indole being added in a 1,4 relationship to the sulfenyl group in each case. High levels of selectivity are influenced by the catalyst system, counterion, and carboxylate group.

Responsibility of small defects for the low radiation tolerance of coated conductors

Abstract Rare-earth-barium-copper-oxide based coated conductors exhibit a relatively low radiation robustness compared to e.g. Nb3Sn due to the d-wave symmetry of the order parameter, rendering impurity scattering pair breaking. The type and size of the introduced defects influence the degrading effects on the superconducting properties; thus the disorder cannot be quantified by the number of displaced atoms alone. In order to develop degradation mitigation strategies for radiation intense environments, it is relevant to distinguish between detrimental and beneficial defect structures. Gadolinium-barium-copper-oxide based samples irradiated with the full TRIGA Mark II fission reactor spectrum accumulate a high density of point-like defects and small clusters due to n - γ capture reactions of gadolinium. This leads to a 14–15 times stronger degradation of the critical temperature compared to samples shielded from slow neutrons. At the same time both irradiation techniques lead to the same degradation behavior of the critical current density as function of the transition temperature J c ( T c ) . Furthermore, annealing the degraded samples displayed the same T c recovery rates, indicating the universality of the defects responsible for the degradation. Since the primary knock on atom of the n - γ reaction as well as the recoil energy is known, we used molecular dynamics simulations to calculate which defects are formed in the neutron capture process and density functional theory to assess their influence on the local density of states. The defects found in the simulation were mainly single defects as well as clusters consisting of Oxygen Frenkel pairs, however, more complex defects such as Gd C u antisites occurred as well.

Circular polarization measurement for individual gamma rays in capture reactions with intense pulsed neutrons

Circular polarization measurement for individual gamma rays in capture reactions with intense pulsed neutrons

Implementation of optically simulated luminescent dosimeter for quality control of gamma ray dose of an accelerator-based neutron source.

Neutron beams utilized for performing BNCT are composed of a mixture of neutrons and gamma rays. Although much of the dose delivered to the cancer cells comes from the high LET particles produced by the boron neutron capture reaction, the dose delivered to the healthy tissues from unwanted gamma rays cannot be ignored. With the increase in the number of accelerators for BNCT, a detector system that is capable of measuring gamma ray dose in a mixed neutron/gamma irradiation field is crucial. Currently, BeO TLDs encased in quartz glass are used to measure gamma ray dose in a BNCT irradiation field. However, this type of TLD is no longer commercially available. A replacement dosimetry system is required to perform the recommended ongoing quality assurance of gamma ray measurement for a clinical BNCT system. The purpose of this study is to evaluate the characteristics of a BeO OSLD detector system under a mixed neutron and gamma ray irradiation field and to assess the suitability of the system for routine quality assurance measurements of an accelerator-based BNCT facility. The myOSLD system by RadPro International GmbH was evaluated using the accelerator-based neutron source designed for clinical BNCT (NeuCure BNCT system). The readout constancy, linearity, dose rate effect, and fading effect of the OSLD were evaluated. Free-in-air and water phantom measurements were performed and compared with the TLD results and Monte Carlo simulation results. The PHITS Monte Carlo code was used for this study. The readout constancy was found to be stable over a month-long period and similar to the TLD results. The OSLD readout signal was found to be linear, with a high coefficient of determination (R2≥0.999) up to a proton charge of 3.6C. There was no significant signal fading or dose rate dependency. The central axis depth dose and off-axis dose profile measurements agreed with both the TLD and Monte Carlo simulation results, within one standard deviation. The myOSLD system was characterized using an accelerator system designed for clinical BNCT. The experimental measurements confirmed the OSLD achieved similar, if not superior to, the currently utilized dosimetry system for routine QA of an accelerator-based BNCT system. The OSLD system would be a suitable replacement for the current TLD system for performing routine QA of gamma ray dose measurement in a BNCT irradiation field.