Abstract Copper radionuclides connect coordination chemistry with diagnostic and therapeutic nuclear medicine. The 12.7 h half-life of 64 Cu and the therapeutic emissions of 67 Cu make radiocopper attractive for peptides, antibodies, prostate-specific membrane antigen (PSMA) ligands, bombesin analogues, hypoxia tracers, and theranostic pairs, although limited 67 Cu access and the low positron-emission probability of 64 Cu constrain translation. The same chemistry creates a stability problem because Cu(II) and Cu(I) prefer different donor environments and geometries. Reduction, proton-assisted decomplexation, and transchelation can therefore alter biodistribution even when release radiochemical purity is high. This review summarizes recent progress in electrochemical evaluation of Cu(II)/Cu(I) redox behavior and coordination stability in copper radiopharmaceuticals, with emphasis on quantitative redox, acid stability, serum stability, radiolabeling, and translational performance data. Non-radioactive copper complexes are discussed as mechanistic models when they clarify redox and coordination behavior relevant to 64 Cu and 67 Cu. The evidence indicates that reduction potential alone is not a reliable stability ranking. Predictive evaluation requires the combination of voltammetric reversibility, ligand geometry, kinetic inertness, biological challenge assays, and vector-specific pharmacokinetics.
Abstract Low-level tritium determination in seawater remains analytically demanding because electrolytic enrichment, liquid scintillation counting and matrix-dependent quench correction must all remain stable at activities close to environmental background. This study developed and statistically validated an integrated alkaline electrolytic enrichment-liquid scintillation counting procedure for high-salinity waters from 0 to 60 PSU. Nine water matrices, including low-background water, artificial seawaters, coastal seawater, estuarine high-salinity water and desalination brine, were processed across 72 independent enrichment measurements. Ion chromatography, ICP-OES, conductivity, pH, ORP, TOC, UV-visible turbidity, FTIR/Raman spectroscopy, XRD, SEM-EDS, XPS and electrochemical impedance spectroscopy were combined with tSIE-based quench tracking to identify matrix-sensitive terms. The uncorrected method showed a progressive negative bias at salinities above 35 PSU, reaching a mean bias of −15.2 % in the 60 PSU matrix. A matrix correction model using salinity, major-ion load, tritium retention and quench index reduced the overall mean absolute bias from 9.4 % to 4.3 %, with mean recoveries of 93.5–102.2 % and expanded uncertainties of 0.026–0.211 Bq L −1 . Minimum detectable concentrations were 0.031–0.044 Bq L −1 after enrichment. Mixed-effects modeling showed that batch-to-batch variance was small compared with salinity-associated quench and retention terms, while PCA separated high-brine matrices through conductivity, tSIE and retention loadings. The workflow therefore provides a practical correction framework for radioanalytical monitoring of low-level tritium in saline marine waters.
Abstract The current research design investigates the potential ameliorative role of broccoli extract against rat pulmonary toxicity produced by nicotine and/or γ-ray exposure in rats. While individual components of broccoli have shown protective effects against either nicotine or radiation separately, the efficacy of whole broccoli extract against concurrent exposure to both agents have not been previously investigated. These findings suggested that the antioxidant activities of broccoli extract are mediated through phenol and flavonoid contents. Broccoli extract has yielded many compounds such as fatty acids, alcohols, esters, and aldehydes identified using GC-MS assay, which exhibited biological activities. The protective role of the broccoli extract against γ-ray- and/or nicotine-induced rat lung toxicity was estimated. A total of 48 rats were categorized into eight groups: control, broccoli (300 mg/kg B.W.), nicotine (4 mg/kg B.W.), γ-ray (8.5 Gy), nicotine + γ-ray, broccoli + nicotine, broccoli + γ -ray, and broccoli + nicotine + γ-ray. The pulmonary tissues were harvested for biochemical and histopathological studies. Pulmonary toxicity was assessed using key biomarkers: hydroxyproline for fibrosis, malondialdehyde (MDA) for lipid peroxidation, superoxide dismutase (SOD) and GPX for antioxidant capacity, and tumor necrosis factor-alpha (TNF-α) and interleukin-6 (IL-6) for inflammation markers, alongside histopathological examination. Exposure to nicotine or γ-rays significantly elevated hydroxyproline, MDA, TNF-α, & IL-6 levels while lowering SOD activity ( p < 0.0001), indicating fibrosis, oxidative stress, and inflammation. The combined nicotine + γ-ray group exhibited the most severe effects. Broccoli extract therapy considerably ameliorated these alterations, returning biomarkers to nearly control levels and improved histopathology results. In conclusion, this preclinical study the broccoli extract attenuates nicotine- and radiation-induced pulmonary toxicity through anti-fibrotic, antioxidant, and anti-inflammatory mechanisms, implying that it may be beneficial as a protective treatment for radiotherapy patients, particularly those with a history of smoking, but direct translation to human application is not yet warranted.
Abstract Excitation functions of the reactions nat Fe(d,x) 55,57,58m+g Co were measured for deuteron energies of 15–35 MeV using the stacked-foil activation technique. The measured cross sections were compared with the available experimental data as well as with model calculations. The model calculations, using the TALYS-2.0 code, reproduced our measured data after a careful selection of a few input parameters. In this work, we report the cross section data with higher precision and extend them above 22 MeV. The thick target yield of 55 Co estimated from the measured excitation function amounted to 45 MBq/μAh for the energy window of E d = 40 → 25 MeV. Using this energy window, 96 % pure 55 Co could be obtained using natural iron target.
Abstract Surrogate nuclear explosion debris (SNED) has emerged as a critical platform for advancing post-detonation nuclear forensic analysis in the absence of readily accessible historic materials. SNED enables controlled investigation and validation of analytical methodologies used to interrogate the chemical, isotopic, radiological, and microstructural signatures preserved in nuclear explosion debris. This review presents an integrated assessment of destructive and non-destructive analytical techniques commonly employed within decision-driven nuclear forensic workflows. Each technique is discussed individually while highlighting how it contributes to different stages of post-detonation analysis. Core methods – including gamma and alpha spectrometry, ICP-MS, TIMS, SIMS, SEM-EDS, XRF, LIBS, vibrational spectroscopy, and X-ray absorption spectroscopy – are critically evaluated with respect to forensic maturity, information content, and matrix limitations. Emphasis is placed on the role of SNED in benchmarking multi-modal workflows and identifying gaps in reproducing heterogeneity, fractionation, and radiation-driven evolution relevant to forensic attribution.
