The role of chlorine as a neutron poison and as a seed for producing radioactive waste in nuclear systems has driven a renewed interest to improve its nuclear data uncertainties. Additionally, basic and applied science programs that use CLYC (Cs[Formula: see text]LiYCl[Formula: see text]:Ce) detectors for neutron spectroscopy and monitoring are also very sensitive to any change in chlorine nuclear data for simulations of the detector response. In this work, sensitivities relevant for these different applications are addressed through simulations of the efficiency of CLYC detectors in a fast fission spectrum when applying new chlorine nuclear data as input. These simulations are validated by an experimental measurement using CLYC detectors coupled to an ionization chamber loaded with a [Formula: see text]Cf spontaneous fission source. The results are then used to obtain the first reliable direct measurement of the [Formula: see text]Cl(n,[Formula: see text]) and summed [Formula: see text]Cl(n,p+n,α) fission spectrum average cross sections, found to be 54.7(32) and 105.0(98) mb, respectively. The results are within uncertainty of calculated fission spectrum averaged cross sections based on recently re-evaluated chlorine nuclear data, which confirm recent impact studies performed for the Molten Chloride Reactor Experiment. Meanwhile, there currently exists only one published criticality benchmark experiment that is sufficiently sensitive to chlorine nuclear data. Discrepancies are found with this set of criticality safety benchmarks, which are more sensitive to thermal and epithermal neutron energies than the energies, above 100keV, tested in this current work. Hence, there is still a need to re-evaluate the chlorine nuclear data at lower energies to assess these discrepancies. Interpretation of the data from future "faster" criticality benchmarks, which are needed for next-gen fast reactor designs, benefit from the improved constraints on the chlorine nuclear data validated in this work.

DDEP evaluation of 40K decay.

Activity standardization and determination of nuclear decay data of 212Pb at LNE-LNHB and first measurements in the SIR at BIPM.

Nuclear decay data evaluation for 212Pb.

Determination of emission intensity for low energy photons following the decay of 109Cd.

Implementation of inverse transform sampling method for photon transport in Monte Carlo code and nuclear data library preparation by NECP-Atlas

ABSTRACT Japan Atomic Energy Agency (JAEA) completed the modification of the STACY critical assembly and resumed operations in August 2024. The purpose of this study is to evaluate the applicability of experimental analysis results using representative Monte Carlo codes and nuclear data for cases with different moderation conditions and critical water heights in the STACY critical experiments. This paper presents the results of experimental measurements and experimental analyses using a simplified computational model for four representative simple symmetric core configurations. The results indicate that typical Monte Carlo calculation codes, combined with evaluated nuclear data, are applicable for analyzing experimental data. Although identifying the sources of slight uncertainty and quantifying their impact in STACY experiments remains a future challenge, the results support future applications in criticality safety research and nuclear data evaluation.

ABSTRACT Paludomidae is a diverse family of limnic gastropods in the Cerithioidea, with a distribution range including most of tropical sub‐Saharan Africa, the Nile Valley, Madagascar, the Seychelles, as well as South and Southeast Asia. Its systematics and taxonomy are currently in a state of confusion, with Thailand being inhabited by probably two distinct species, viz. Paludomus petrosa (Gould, 1843) and Paludomus siamensis Blanford, 1903. We examined available type material and used qualitative and quantitative shell characters in combination with multivariate ratio analysis (MRA), as well as molecular species delimitation approaches on the basis of mitochondrial and nuclear markers, that is, phylogenetic tree reconstructions, automated barcode gap discovery (ABGD) and the Bayesian variant of the general mixed Yule‐coalescent (bGMYC) approach, to test the validity of these two species. Our results confirm the presence of two morphologically distinct species in Thailand. Furthermore, we show that MRA allows us to translate the results of multivariate statistics into relations of body ratios that, along with qualitative characters, can be used to reliably identify these two species. The mitochondrial and nuclear sequence data, as a second line of evidence, corroborate our morphological findings. Paludomus petrosa and P. siamensis are re‐described, and regional distribution patterns of these species in Thailand are discussed, with a focus on the potential role of the Isthmus of Kra in separating these populations at an earlier stage.

The properties of neutron excess gallium nuclei are predicted utilizing a single-particle model. The single particle model calculations include alpha, beta, positron, electron capture, and spontaneous fission decay modes. Neutron emission decay modes that have short half-lives are not readily determined by the model. However, estimates of the neutron decay mode were evaluated using the methodology of Chowdhury et al. Using that model, spontaneous neutron emission is predicted to occur in the range of A = 97 – 99. The Japanese Nuclear Data Compilation calculations terminate their calculations at A = 92. Given these results, single-particle model calculations are extended to encompass these values, and were extended to A = 101. Single particle model calculations predict that A = 87 – 101 neutron excess gallium systems form bound systems that have limiting beta decay half-lives in the range of 0.707 – 28.6 ms. Model half-life results for the A = 87 – 92 gallium nuclei are within a factor of about two of the predictions of the Japanese Nuclear Data Compilation calculations.

Spent tri-structural isotropic (TRISO)–based fuels have a strong track record in storage and transportation without documented incidents. This work seeks to reduce uncertainty to aid in more informed spent fuel management of TRISO-based fuels by modeling both fresh and spent pebble bed reactor (PBR) fuel and comparing the results to the regulatory standards from 10 CFR 71. SCALE was used for all modeling due to it having fast and accurate methods for handling PBR fuel modeling, as well as having an efficient method for shielding calculations in monaco with automated variance reduction using importance calculations (MAVRIC), which utilizes the consistent adjoint-driven importance sampling (CADIS) and the forward-weighted consistent adjoint-driven importance sampling (FW-CADIS) methods. KENO-VI was used for all criticality calculations, TSUNAMI was used for uncertainty quantification on k-effective, TRITON and the Oak Ridge isotope generation code (ORIGEN) were both used for depletion of the fuel, and MAVRIC was used for shielding calculations. For criticality assessments, this study focused on the requirement that the value of the neutron multiplication factor, k-effective (k-eff), would not exceed a peak value of 0.95, including uncertainty, with 95% confidence. Criticality was initially examined by modeling fresh fuel from three different designs—HTR-10 fuel, PBMR-400 fuel, and demonstration fuel representative of a TRISO-fueled modern high-temperature gas reactor (HTGR) design, henceforth referred to as Demo HTGR—and placing them into various sized containers with conditions described in 10 CFR 71 to quantify the peak k-eff state. When the peak value of 0.95 k-eff was exceeded, mitigation methods were examined in those scenarios. Burnup credit, pebble displacement in areas of strong neutron multiplication, and random pebble replacement using pebbles of various compositions and replacement fractions were examined. In summary, the criticality of PBR fuels can be well accounted for by restricting container size, taking credit for burnup, or by displacing/replacing pebbles. Uncertainty of the k-eff due to nuclear data uncertainties was recorded at ~0.6644%Δk/k, or roughly 664% mil (pcm). The nuclear data–induced uncertainty was relatively small and should not require significant modification in the design to be accounted for. Revisions to the evaluated nuclear data file values have been shown to have a larger impact than nuclear data–induced uncertainty. For dose rate aspects, U.S. Nuclear Regulatory Commission regulations require a maximum dose rate of 10 millirem per hour (mrem/h) at 2 meters. In examining the dose rate behavior of spent PBR fuel, the representative Demo HTGR fuel was modeled exclusively due to it possessing the highest target burnup of the examined fuels. Equilibrium cycle modeling methods were used to produce a higher-fidelity discharge isotopic composition than simple assumptions, such as reflected pebbles. The discharge composition was used as a source term in the fixed-source transport shielding calculations, and dose rates were calculated at 2 m for the shortest possible cooling time. The low concentration of fuel material led to dose rates that were in line with regulatory limits, despite the high burnup when compared to traditional light water reactor fuels. The methods employed in this study would require more work to further verify and validate and are limited to the criticality and dose rate analyses performed.

Recently, the International Commission on Radiological Protection (ICRP) has released adult and pediatric mesh-type reference computational phantoms (MRCPs) through its Publications 145 and 156, which incorporate anatomically refined respiratory tract structures that overcome the limitations of earlier voxel and stylized models. In this study, a comprehensive dataset of specific absorbed fractions (SAFs) and radionuclideSvalues was generated for the respiratory tract across the entire age- and sex-specific series of ICRP MRCPs. The phantoms were implemented in the Geant4 Monte Carlo radiation transport code (version 11.3) to compute SAFs for photons, electrons, and alpha particles over the energy ranges of 0.001-10 MeV for photons and electrons and 1-12 MeV for alpha particles, with certain low-energy values supplemented by a limiting SAF interpolation approach. The calculated SAFs were subsequently combined with nuclear decay data from ICRP Publication 107 to derive S values for all relevant source regions following inhalation exposures to radionuclides. Photon and electron SAFs were obtained for 36 source-target combinations, and alpha SAFs for 18 combinations, whileSvalues were produced for 1,252 radionuclides. The calculated SAFs exhibited clear age-dependent trends, with larger values in younger phantoms. Furthermore, the calculated SAFs andSvalues were generally greater than previously reported ICRP values. The complete dataset is available through an open-access repository, representing the first effort to provide SAFs andSvalues for the respiratory tract using the ICRP MRCPs. The calculations explicitly accounted for micrometre-scale source and target regions within anatomically realistic respiratory tract structures, while also incorporating inter-tissue irradiation cases, which had not been possible with previous models.

Nuclear data bears a critical nexus with marine radioactive pollution surveillance, serving as the evidentiary foundation for source attribution and impact assessment. This article adopts an empirical research approach, integrating nuclide simulation modeling with radioactive monitoring data, to demonstrate that Japan's discharge of Fukushima radioactive wastewater has resulted in the dispersion of radionuclides from inland waters into the North and West Pacific Transition Zones via ocean currents, thereby posing potentially irreversible, multigenerational threats to marine ecosystems. The current deficiencies in the international legal governance framework for marine pollution-combined with weak legal enforcement, a low level of cooperative consensus, and a transparency deficit in radioactive pollution monitoring-further exacerbate these risks. Accordingly, employing a doctrinal research method, this article examines the legal foundations for a Pacific Rim regional nuclear data regulatory framework and proposes a regional legal cooperation mechanism composed of legal principles, legal rules, organizational structures, and operational procedures. By constructing such a mechanism, the transparency of radioactive waste disposal monitoring data can be enhanced, the legal accountability challenges arising from Japan's wastewater discharge mitigated, and regional consensus strengthened on nuclear data classification, monitoring, and disclosure-ultimately improving the safety of nuclear energy development and utilization within the Pacific Rim.

Introduction: Plasma triglyceride (TG), mostly embedded in apoB-containing particle (apoB-P), has been proposed as a potential residual risk factor for atherosclerotic cardiovascular disease (ASCVD). However, the atherogenicity of TG in different types of ApoB-P, especially the causality, remains unclear given that the per-particle atherogenicity varies among different types of apoB-P. Research questions: To investigate the association TG content in various types of ApoB-P with the risk of coronary artery disease (CAD) in both observational and genetic study. Methods: Observational study was conducted in 169 301 UK Biobank participants with complete nuclear magnetic resonance lipoprotein profiling data and without a history of ASCVD, diabetes, or lipid-lowering therapy. Multivariate Cox proportional hazard regression was used to determine the association between TG levels in different apoB-P and risk of incident CAD. Genetic study was performed using individual-level data from 472 495 UK Biobank participants of European ancestry. One-sample mendelian randomization (MR) was performed with weighted polygenic scores as instrumental variables, which were calculated with genetic variants strongly associated with TG in various subfractions of ApoB-P. Results: In the observational study, very-low-density lipoprotein (VLDL) TG (adjusted hazard ratio [aHR] per one standard deviation [SD], 1.04; 95% CI, 1.02 - 1.06), intermediate-density lipoprotein (IDL) TG (aHR per one SD, 1.10; 95% CI, 1.08-1.12) and low-density lipoprotein (LDL) TG (aHR per one SD, 1.09; 95% CI, 1.07-1.11) were each individually associated with incident CAD. When subfractions of apoB-P were taken into account, the aHR were higher with TG in smaller size VLDL, ranging from 1.03 (95% CI, 1.01 - 1.05) for extra extra large VLDL TG to 1.08 (95% CI, 1.06 - 1.10) for extra small VLDL TG, whereas lower with TG in smaller size LDL, ranging from 1.06 (95% CI, 1.04 - 1.08) for small LDL TG to 1.10 (95% CI, 1.08 - 1.12) for large LDL TG. In one-sample MR, odds ratios (95% CI) per one SD higher genetically predicted VLDL TG, IDL TG, and LDL TG were 1.16 (1.12 - 1.21), 1.34 (1.29 - 1.39), and 1.37 (1.32 - 1.42) for CAD, respectively. Conclusions: The atherogenicity of both observed and genetically determined TG in apoB-P differs with regard to different particle size. The present observation reinforced the atherogenic mechanism of different apoB-P and shed light on critical target of TG-lowering strategy.

Abstract Extensive use of radiochemical methods has been made over decades in radionuclide development work at different cyclotrons at the Forschungszentrum Jülich. In this article, a brief overview of the methods used in investigations on nuclear data, high-current targetry, chemical processing, etc. is given, with some typical examples in each area. The large and clinical scale productions of some standard and non-standard positron emitters, respectively, using the proton and deuteron beams at a small cyclotron are elaborated. Furthermore, some ongoing development work on two therapeutic radionuclides of great current interest, namely 193m Pt and 211 At, using the α-particle beam at the new medium-sized cyclotron, is described.

Phylogenomic insights into incomplete lineage sorting and hybridization in early-diverging eudicots.

Deep neural network predictions for excitation functions of 165Ho(α,xn) reactions.

Interpretable deep learning unlocks high-fidelity prediction for medical radioisotope production.

Unraveling the conformational landscape of amyloid precursor protein intracellular domain.

Enhancement of biopharmaceutical properties of oxytetracycline hydrochloride through β-cyclodextrin complexes and its photodegradation by metallic nanoparticles.

Research on automatic labeling of nuclear power equipment operational history data based on large language models