Erratum to: Preparation of High-Labeled Graphene Oxide by Tritium Thermal Activation Method for Application in the Betavoltaic Cell of a Nuclear Battery

2024-6-1

Structure and IR Spectroscopic Study of Sodium Tris(monoiodacetato)uranilate

2024-6-1

Pathways for Activating Isotope Exchange of Dopamine with D2O

2024-6-1

Disproportionation of Plutonium(V) in EDTA Solutions

2024-6-1

Study of the Activation Process of Isotope Exchange between Boc-Trp-Pro-Pro-Trp, Trp-Pro-Pro-Trp and Deuterated Water

2024-6-1

Neptunium(VI) Nitrate Complexes with Urea and Terpyridine Derivatives

2024-6-1

Features of the Sorption Interaction of [3H]Hyaluronic Acid with Hydroxyapatite

2024-6-1

Hydrogen Peroxide in the Chemistry of f-Elements

2024-6-1

Erratum to: Nanodiamonds as Lutetium-177 Carriers for Nuclear Medicine

2024-6-1

Production of 105Rh Using Electron Accelerators and a New Method for Its Recovery from Irradiated Targets

2024-6-1

Sorption Recovery of Cesium from High Level Alkaline Waste from Mayak Production Association

2024-6-1

Development of Immunoradiometric Assay Technique for Measurement of Luteinizing Hormone in Human Serum

2024-6-1

Development of a Neutron Activation Analysis Method for Studying the Elemental Composition of Atherosclerotic Plaques

2024-6-1

Erratum to: Statistical Evaluation of the Tritium Content of Aquatic Ecosystems at NPP Sites

2024-6-1

Thermal Stability of Irradiated VP-1AP Anion Exchange Resin

2024-6-1

Technology for Reprocessing Mother–Wash Solution after Crystallization Purification of Spent Nuclear Fuel from High Temperature Gas-Cooled Reactor

2024-4-1

Retrospective Estimation of Potential Mobility of Artificial Radionuclides (60Co, 137Сs, 152Eu, 154Eu) in Bottom Sediments of the Yenisei River

2024-4-1

Determination of the Thermal Stability of Impregnated Type Solid Extractant Based on Dibenzo-21-crown-7 and Organic Matrix MN-200

2024-4-1

Diffusion of Radioactive Waste Elements from Underground Water and Leachates of Phosphate Waste Forms in Pore Solution of Clay Materials

2024-4-1

Dynamic Tests of Cesium-137 Recovery from the Mayak Model Alkaline HLW with p-Isononylcalix[6]arene-based Extractant

2024-4-1

Nanodiamonds as Lutetium-177 Carriers for Nuclear Medicine

2024-4-1

Obtaining of Nanodiamond Conjugates with Scandium Isotopes for the Use in Nuclear Medicine

2024-4-1

The Influence of the Sizes of Nanodiamond Aggregates in Suspensions on the Efficiency of Sorption of 90Y and 177Lu Isotopes for Further Use in Nuclear Medicine

2024-4-1

Preparation of High-Labeled Graphene Oxide by Tritium Thermal Activation Method for Application in the Betavoltaic Cell of a Nuclear Battery

2024-4-1

Effect of High-temperature VVER-1000 SNF Reprocessing Time on the Extent of Fission Product Removal

2024-4-1

XPS Determination of the Oxidation State of 99Тс Isotope Absorbed on the Surface of Pyrrhotite FenSn+1 and Stibnite Sb2S3

2024-4-1

Lithium, Sodium, and Strontium Fluoroglutaratouranylates: Structure and Some Properties

2024-4-1

Aspects of Modeling of the Degradation of Engineered Safety Barriers Based on Portland Cement in Radionuclide Migration Problems

2024-4-1

Evaluation of Natural Radioactivity in Soil Samples Collected from the Khasa River Banks in Kirkuk, Iraq

2024-4-1

Statistical Evaluation of the Tritium Content of Aquatic Ecosystems at NPP Sites

2024-4-1

Specific Features of Reduction of Plutonium(VI) Ozonation Products in Solutions of Various Nature Alkalis

2024-4-1

Speciation of Uranium in Trace Concentrations in Aqueous Solutions of Complex Chemical Composition

2024-4-1

Distribution of Np, Pu, and Am in Water, Suspended Matter, and Bottom Sediments of Peter the Great Bay

2024-2-1

Cast Stone Matrix Based on Comelts of Basalt and Metal Oxides. Part II. Basalt–ZrO2 System

2024-2-1

Cast Stone Matrix Based on Comelts of Basalt and Metal Oxides: Part I. System Basalt–MxOy (M = Sr, Ln)

2024-2-1

The Use of D2 and Deuterated Water for the Introduction of a Label into 4-Aminobutanoic Acid

2024-2-1

Partitioning of the High Level Radioactive Waste from the Purex Process by 40% TBF in Isoparaffin Using Magnesium Nitrate as a Salting-out Agent

2024-2-1

Distribution Features of 238U, 232Th, and 226Ra in Bottom Sediments of the Shelf and Continental Slope of Svalbard

2024-2-1

Sorption Treatment of Nitric Acid Solutions to Remove Tributyl Phosphate and Hexachlorobutadiene

2024-2-1

Sorption Treatment of Aqueous and Organic Media to Remove Tributyl Phosphate and Acidic Products of Its Decomposition

2024-2-1

Influence of Soil Degradation on Radiation-Chemical Transformations of Oil

2024-2-1

Effect of Irradiation on the Thermal Stability of Nitric Acid Solutions of Carbohydrazide

2024-2-1

Comparison of Dynamic Tests of the Modified Purex Process Flowsheet Using 30 and 45% TBF in Isoparaffin

2024-2-1

Preparation of Uranium/Plutonium Oxide Solid Solution Powder from Ammonium Uranyl–Plutonyl Carbonate in a Laboratory Microwave Unit

2024-2-1

Uranium-Bearing Cast Stone Matrices

2024-2-1

Influence of Gamma Radiation on the Composition and Physicochemical Characteristics of Olefins: Post-Radiation Effects

2024-2-1

Release of 137Cs into the Gas Phase during the Interaction of 137Cs Compounds with Molten Lead

2024-2-1

Comparative Analysis of UN and UO2 Oxidation in Air and Nitrogen Hemioxide

2023-12-1

Behavior of Niobium-95 in Techa River Water

2023-12-1

Sorption of Sr(II) Ions with Tricalcium Phosphate in the Presence of Humic Acids

2023-12-1