Neutron imaging suffers from severe white spot noise characterized by high intensity, random spatial distribution, and resistance to conventional filtering, significantly degrading image quality and obscuring critical structural details. To address this challenge, we propose DFGU-Net (Dual-stage Feature-Gated U-Net), a novel self-supervised denoising framework that leverages intrinsic statistics from single noisy observations. The method integrates three key components: harmonic mean filtering for initial high-intensity noise suppression, a cascaded coarse-to-fine architecture for progressive structural restoration, and a gated feature fusion module for adaptive multi-level feature integration. Comprehensive experiments on the SIXray dataset demonstrate superior performance, achieving PSNR and SSIM improvements of 1.57 dB and 0.036 over S2S-NR, respectively. On real thermal neutron images, the method reduces BIQI and NIQE scores by 4.43 and 0.013, respectively, outperforming classical approaches (BM3D) and state-of-the-art deep learning methods (DnCNN, SUNet, GAN-based models) in both quantitative metrics and perceptual quality. The proposed framework strikes an effective balance between computational efficiency and restoration accuracy, making it suitable for practical deployment in neutron-based non-destructive testing applications.

Abstract Boron neutron capture therapy (BNCT) is an emerging binary cancer radiotherapy with significant advantages in the precise ablation of tumors in comparison to other therapies. Its clinical efficacy has been validated in the treatment of locally invasive tumors such as gliomas, melanomas, and osteosarcomas. Boron carriers are the cornerstone of effective BNCT, and boronophenylalanine and sodium borocaptate are clinically approved boron agents to date. The former suffers from low boron content, necessitating repeated administration, while the latter lacks tumor selectivity and causes nonspecific damage to normal tissues. Boronated nanomedicines, characterized by high boron loading capacity and potent tumor-targeting ability, offer opportunities for achieving optimal clinical outcomes in BNCT. This review summarizes the research advances in various boronated nanomedicines over the past decade and introduces the relevant research efforts dedicated to the sensitization of BNCT. It also highlights the research progress of BNCT combined with immunotherapy, chemotherapy, gene therapy, and photothermal therapy and finally concludes the application of non-10B-enriched boronated nanomedicines in BNCT. Furthermore, this paper discusses in depth the challenges and breakthroughs encountered during the clinical translation of boron-containing nanomedicines and provides insights into the development of next-generation boron-based nanomedicines.

This study presents an ultra-compact deuterium-deuterium (DD) neutron generator with a self-moderating structure, designed for prompt gamma neutron activation analysis (PGNAA) and thermal neutron imaging. The key innovation is its integrated moderator, which directly converts DD fusion neutrons into the required thermal neutrons. Remarkably, this compact device (maximum dimension: 34.6 cm) achieves a peak neutron yield of 2.14 x 109 n/s at-100 kV and 13.7 mA. Furthermore, this study conducted a systematic analysis of the neutron source characteristics, including neutron energy spectrum, fluence distribution, dose, and angular distribution, using a combined approach of Geant4 Monte Carlo simulations and experimental measurements. Results demonstrate that the thermal neutron flux at the moderator surface reaches 4.17 x 104 n center dot cm-2 center dot s-1), representing 13.5 % of the total neutron fluence. This compact generator serves as a high-performance source of fast, epithermal, and thermal neutrons, providing robust theoretical and experimental foundations for subsequent neutron source optimization and application studies.

Conventional radiotherapy compromises antitumor immunity through collateral damage to immune cells. While boron neutron capture therapy (BNCT) enables tumor-selective 10B (n, α) 7Li reactions, clinical agents like boronophenylalanine (BPA) suffer from excessive dosing and exhibit immune-metabolic inertia. We report a biomineralized albumin-based BNCT agent (Albumin@MnB) synthesized from clinically accessible borax, manganese, and albumin, which unlocks neutron capture-triggered immunotherapeutic activation. Albumin@MnB achieves potent tumor suppression at reduced boron doses, demonstrating superior efficacy compared with BPA. Importantly, Albumin@MnB enhances intratumoral immune cell infiltration and suppresses distant tumor growth, synergizing with adoptive T cell immunotherapy and immune checkpoint inhibitors. By integrating tumor-specific radiolytic energy deposition with metabolic reprogramming and immune activation, this strategy establishes boron neutron capture immunotherapy (BNCI) as a multimodal therapeutic paradigm that bridges targeted radiolysis with systemic antitumor immunity.

This study attempted to apply a helicon plasma source to a compact Deuterium-Deuterium (D-D) neutron generator, ultimately achieving a maximum neutron yield of up to 1.27 & times; 10(9) n/s with stable operation for over 1 h. By investigating deuterium plasma characteristics with a Nagoya-III antenna in a permanent magnet helicon device, we established a correlation between its atomic spectral lines and plasma density. The results show that the transition power for deuterium plasma from the inductively coupled mode (H mode) to the magnetically enhanced inductively coupled mode (ME-H mode) is similar to 400 W. However, constrained by the maximum power limit of the matching network (1000 W), we were unable to achieve wave coupled mode (W-mode) operation. Then, based on the discharge characteristics of the helicon deuterium plasma, a compact D-D neutron generator utilizing helicon deuterium plasma was constructed, and experiments on deuterium ion beam extraction were carried out. It was observed that when the discharge mode transitions from H-mode to ME-H-mode, the extracted beam intensity increases several-fold. Furthermore, there exists an optimum gas feed rate that maximizes the extracted beam intensity, and compared to inductively coupled ion sources, the system demonstrates higher gas-utilization efficiency. Although the power limitation of the matching network prevented the helicon discharge from reaching W-mode, the results of this study confirm the distinct advantages of helicon plasma sources for application in compact D-D neutron generators, thereby laying the groundwork for the further adoption of helicon ion sources in this field.

A miniaturized fast neutron imaging detector based on scintillating fiber (Sci-Fi) is designed to adopt a SiPM array as its photoelectric conversion component. The center of gravity (CoG) method, widely used for neutron event positioning, demonstrates limited effectiveness when applied to signals originating from the peripheral regions of the array. To address this issue, the present study conducted a simulation analysis of the light output distribution characteristics from both the Sci-Fi and the associated light guide using the Geant4 toolkit. The photon distribution functions fitted for various regions all exhibited correlation coefficients exceeding 0.99. Furthermore, this work categorized the deviations encountered during the operation of the imaging detector into three principal types: inherent deviations, hardware-induced deviations, and algorithmic deviations. Focusing on algorithmic deviations, scintillation photon events randomly distributed within the Sci-Fi array were simulated. An inversion method, developed based on the photon distribution function, employed an iterative computational approach to accurately determine event positions by optimizing the fit. Compared to the CoG method, the inversion technique achieves a reduction in average positional deviation by over 13%, sustains robust positioning performance for events occurring near the array edges, enhances the effective utilization of the SiPM array, and is well-suited for applications demanding higher spatial resolution and an expanded field of view.

The Institute of Energy, Hefei Comprehensive National Science Center has developed a high-yield compact deuterium-deuterium neutron generator for neutron imaging based on a RF ion source. After multiple technical iterations, a maximum neutron yield of 2.09 x 1010 n/s has been successfully achieved. Furthermore, the neutron yield has stably operated above 1 x 1010 n/s for 3 h, with an effective operating time exceeding 99.8 %. This result lays a solid technical foundation for the application of neutron imaging in the future and marks the first reported neutron source based on a RF ion source to achieve a neutron yield exceeding 1010 n/s.

In order to meet the demand for neutron detection in extreme environments with high temperature, high pressure, and strong radiation, different Schottky-type microstructure neutron detectors based on the wide bandgap semiconductor material 4H-SiC are designed in this work. Detectors D1 and D2 used nickel (Ni) and high melting point tungsten (W) as the front Schottky contact electrode metals, respectively, while detector D3 added a silicon dioxide (SiO2) interlayer at the W metal-semiconductor interface. Current-voltage measurements show that the detectors D1-D3 have typical Schottky rectification characteristics. The transient current pulse response of the detectors is affected by different applied bias voltages and incident particle energies. At room temperature, the detector D3 with SiO2 interlayer shows the highest neutron detection efficiency of 6.57%. It also demonstrates that the SiO2 interlayer can reduce the leakage current due to high surface states and surface damage generated during process fabrication. The neutron irradiation of the detectors at high temperature (150 degrees C) is also studied, and very small differences in the energy spectra of the detectors are observed compared to those in a room-temperature environment, demonstrating that the 4H-SiC-based Schottky-type microstructure neutron detectors have the capability of detecting neutrons at high temperatures as well.

A solid-state lithium (Li) target for 2.5 MeV, 20 mA proton beam (PB) accelerator boron neutron capture therapy (BNCT) was developed at the Energy Research Institute of Hefei National Comprehensive Science Center (Anhui Energy Laboratory). The Li target must withstand a high heat flux (HHF) of up to 2.8 MV/m2 generated by the PB bombardment. The research team designed an optimized cross-rib structure. To test the thermal removal ability of the structure, electron beam thermal loading experiments verified its effective performance. The results showed that the designed Li target meets the requirement to remove the thermal load generated by the PB (2.8 MW/m2).

As a key technology connecting physical entities and virtual models, digital twin builds a bridge and bond for the exchange and sharing of virtual and real elements. In view of the complexity of the special equipment structure of accelerator neutron source (ANS), the lack of real-time mapping of the running state of the equipment, and the low degree of simulation, the research and implementation framework of the key technologies of the DT(Digital Twin)-driven visual operation and maintenance platform of the ANS (VOMPA) was proposed. It includes five parts: digital model construction of the ANS, multi-source heterogeneous data acquisition and monitoring of the ANS, yield prediction and performance optimization of the ANS, fault diagnosis and health assessment of the ANS, and maintenance strategy and health management of the ANS. Through the research on the above key technologies, a whole process operation mechanism is constructed, which includes 3D(Three dimensions) dynamic visual monitoring of ANS, full-process driving of digital twin, multi-parameter optimization of neutron yield, comprehensive analysis of fault prediction and intelligent maintenance strategy, so as to realize the service requirements of reflecting reality by virtual reality, controlling reality by virtual reality, optimizing reality by virtual reality, and prerealizing reality by virtual reality. It can effectively avoid equipment damage caused by accidental failure and further improve the production and operation efficiency of the ANS.

Boron neutron capture therapy (BNCT), which uses high-energy particles generated by the reaction of 10B isotope with thermal neutrons to kill tumor cells precisely at the microscale, has become a promising treatment approach with aggressive and recurrent cancers. The development of highly selective boron drugs for tumor cells and devices with thermal neutron beams is crucial for BNCT. Borophenylalanine (BPA), the most widely used 10B containing drug in clinic, has problems with fast metabolism and poor tumor retention. Therefore, to improve the therapeutic effect of BPA, this study reports highly 10BPA-loaded platinum nanoparticles (Pt-10BPA NPs) and conduct BNCT experiments with a neutron beam generated by an accelerator neutron source. The Pt-10BPA NPs achieve deep tumor penetration and retention, thereby significantly inhibiting the growth of subcutaneous colorectal tumors in mice. Furthermore, unlike classic drugs, the Pt-10BPA NPs have superior catalytic properties and can sensitize BNCT by increasing reactive oxygen species (ROS) production. Since the observation of improvements in immune responses induced by Pt-10BPA NPs sensitized BNCT, its further combination with immune checkpoint blockade therapy results in significant suppression of both primary and secondary tumors. In summary, this study provides a new aspect for the development of catalytic nanomedicines for BNCT sensitization.

The present paper presents a compact D-D neutron generator designed for imaging applications, capable of producing a neutron yield exceeding 109n/s. Here, a RF ion source ignited by an external antenna is envisaged, and the discharge chamber's design involves a double-layer glass cylinder for active cooling of the discharge chamber. At the same time, by improving the chamber's size and strategically positioning the magnetic field outside -multi-cusp and top magnetic field, the efficiency of the ion source is enhanced, including increased the extract beam current and extended ion source life, thus fostering increased neutron production and prolonged service duration. The experimental results show that under the condition of RF power 400 W and high voltage negative 95 kV, the beam current is extracted by 9.5 mA, and the stable operation of 24 h is realized, which the neutron yield reaches 1.1 x 109 n/s with effective operation time surpassing 95 %.

This article presents a systematic optimization of a compact deuterium-deuterium neutron generator based on a RF ion source, significantly increasing the neutron yield by 6 times to 6.46 x 109 n/s. The designed device employs a concave high-voltage vacuum feedthrough, increasing the overall breakdown strength of the device to 150 kV. Additionally, to improve the ion current extracted, an innovative 'diffusion-type' plasma chamber has been adopted, achieving an increase of over 20 % in beam extraction. Furthermore, it has been verified that under high thermal load conditions, the performance of the scandium target is superior to that of the titanium target, primarily due to the higher desorption temperature of deuterium from scandium compared to titanium. Finally, a stable neutron yield of over 5 x 109 n/s was achieved, with an effective operating time exceeding 98 %. This result provides a solid technical foundation for further improving neutron imaging quality.

Monte Carlo calculations are extensively used in the fields of nanodosimetry and DNA damage research. Presently, the focus of DNA repair simulation studies is predominantly on the temporal aspects of the repair process, the impact of radiation dose on DNA repair requires further investigation. Caenorhabditis elegans ( C.elegans ) is one of the important model organisms in radiation biology research, and its germ cells are closely related to the DNA damage. Using the Hilbert curve, the DNA germ cell of C. elegans was constructed, and the double-strand breaks (DSB) yields quantified by Geant4-DNA. After comparing the simulation results of total DNA damage and cluster damage with biological data, it was found that the simulation results of cluster damage are close to the biological data. The number of DSBs induced by Cs-137 radiation was further compared with experimental data at different doses and proposed a damage repair model for the number of DSBs in the germ cell of C.elegans that is related to the dose.The repair fitting was conducted for both total DSB damages and DSB cluster damages. After the application of the repair model fitting for the two types of DNA damage mentioned above, the results matched well with the corresponding biological experimental data (R-2 > 0.950).

Gadolinium-neutron capture therapy (Gd-NCT) employs isotopically enriched Gadolinium (Gd) and thermal neutrons to selectively target cancer cells. This study investigated the targeting efficacy of 157Gd-DOTA-PSMA (Prostate-Specific Membrane Antigen) in prostate cancer and explored its potential applications in Gd-NCT. We developed 157Gd-DOTA-PSMA, a novel theranostic bio-gadolinium agent specifically designed for magnetic resonance imaging (MRI)-guided Gd-NCT. 68 Ga-DOTA-PSMA positron emission tomography-computed tomography (PET/CT) imaging showed peak radiotracer uptake at 2 h post-injection, with a tumor-to-non-tumor (T/NT) ratio of 6.95 ± 0.60. MRI analysis confirmed a stable T1 signal enhancement 2 h post-injection. Time-of-flight inductively coupled plasma mass spectrometry (TOF-ICP-MS) revealed significantly elevated Gd concentrations in 22Rv1 tumor compared to PC-3 tumor and other healthy organs. ICP-MS analysis showed Gd concentrations of 165.69 μg [Gd]/g in 22Rv1 tumors and 35.25 μg [Gd]/g in blood, yielding a tumor-to-blood (T/B) ratio of 4.65 ± 0.54 and a T/NT ratio of 3.65 ± 0.49. Neutron irradiation with 157Gd-DOTA-PSMA reduced cell viability, inhibited colony formation, and induced DNA damage and apoptosis in 22Rv1 cells. In 22Rv1 mice, γ-H2AX levels peaked at 6 h post-irradiation, accompanied by an increase in pro-apoptotic proteins and a decrease in anti-apoptotic proteins over 24 h. In the NCT group following the injection of 157Gd-DOTA-PSMA, there was effective suppression of tumor growth without a loss of body weight, resulting in a 1.7-fold increase in median survival compared to control group. 157Gd-DOTA-PSMA, as a theranostic bio-gadolinium agent designed for targeted Gd-NCT in prostate cancer, represents a novel therapeutic approach and broadens the scope of potential applications of neutron capture therapy.

A scandium target design scheme for a compact Deuterium-Deuterium neutron generator aimed to 1010 n/s neutron yield was proposed in this paper. Firstly, the cold-water channel structure (the cooling fin type, double spiral and single spiral cooling channel) was studied based on solid-heat coupled analyses. The results indicated that the cooling fin type cooling channel structure could effectively maintain the surface temperature of scandium below 450 degrees C in condition of total beam power reaching 5 kW to meet the needs of use, comparing the other two type structures. Subsequently, the study examines the effects of various factors such as scandium film thickness, heat exchange area, water flow rate, and thickness of the scandium film carrier on heat load removal, all within the context of the cooling fin cooling channel structure. The results implied that the thickness of the scandium film played a dominant role in heat removal effects compared to the thickness of the film carrier and the water flow rate. Further, the influences of cooling water flow on the stress and strain of scandium target were investigated in detail using flow-solid-heat analyses. The outcomes suggested that the maximum stress of scandium film decreases gradually with the increase of water flow. Finally, the CFT was tested for discharge, and it could operate stably at a neutron yield of 109 n/s.

Gadolinium-neutron capture therapy (Gd-NCT) employs Gadolinium (Gd) isotopes and thermal neutrons to specifically target and kill cancer at cells level. This study investigates the targeting efficacy of 157Gd-DOTA-HK (DHK), a novel agent designed for Gd-NCT and MRI. We synthesized 157Gd-DHK, which combines a Gd-DOTA complex as a neutron capturer and MRI probe with αvβ6 binding peptide (HK) for targeted Pancreas adenocarcinoma (PDAC) therapy. 157Gd-DHK demonstrated a significantly high binding affinity for BxPC-3 cells. scintigraphy revealed that the optimal time window for Gd-NCT was 26 h after injection. The conjugate’s imaging capabilities and its potential as an MRI contrast agent were validated. The conjugate effectively triggered nuclear reactions via Gd-NCT, leading to efficient tumor cell destruction. Photon sensitization studies showed that 157Gd-DHK induced photon-mediated phototoxicity in cancer cells while exhibiting minimal toxicity. 157Gd-DHK shows great potential as a theranostic agent for targeted imaging of PDAC and Gd-NCT applications. It presents a novel strategy to enhance the specificity and efficacy of Gd-NCT in cancer treatment.

This paper presents the 2-D numerical simulation results of the heavy-ion-induced single-event leakage current (SELC) degradation and single-event burnout (SEB) in the silicon-carbide (SiC) avalanche photodiode (APD). The employed simulation physics models and material parameters are validated by the reverse I-V characteristics and spectral response characteristics in experiments. The region most sensitive to heavy ion is identified. Then, the SEB failure behavior of SiC APD is investigated. Based on the analysis of ion-induced SELC degradation or SEB failure, three hardening methods-modifying the mesa etch depth, introducing Low Carrier Lifetime Control (LCLC) region, and inserting buffer layer-are investigated. As a result, the effects of three hardening methods on the electrical properties and SEB performance for SiC APD are compared.

A deuterium-deuterium neutron generator device based on the 2.45-GHz electron cyclotron resonance technique has been designed. The device achieves a neutron yield of 5 x 108 n/s supplied by the ion source with a beam current of 5 mA. The device is intended for use in radiation modification, isotope production, prompt gamma neutron activation analysis, and boron neutron capture therapy studies. In this work, we study the effects of stainless steel, glass, and aluminum (Al) chamber linings with boron nitride (BN) and glass front plates on both the ion source-induced beam quality and the neutron source yield. The results show that the combination of an Al chamber liner with a BN front plate liner increases current and neutron yield by three to four times compared to other combinations. Stable Al2O3 films generated on the Al surface in air, as confirmed by X-ray diffraction pattern analysis, have a high secondary electron emission coefficient and low wall recombination coefficient, which contributes to the generation of D+ ions in the chamber. As a result, the ion source current and neutron generator yield are improved.