ROLE OF NUCLEAR POWER IN LARGE-SCALE POWER PRODUCTION IN RUSSIA IN THE 21ST CENTURY
SVBR-75/100 MULTIPURPOSE MODULAR LOW-POWER FAST REACTOR WITH LEAD–BISMUTH COOLANT
HEAVY LIQUID METAL COOLANT – LEAD–BISMUTH AND LEAD – TECHNOLOGY
CORROSION-MECHANICAL STRENGTH OF STRUCTURAL MATERIALS IN CONTACT WITH LIQUID LEAD
LEAD–BISMUTH AND LEAD COOLANT IN A NEW TECHNOLOGY FOR REPROCESSING LIQUIDS AND GASES
OPTIMIZATION OF CONCEPTUAL SOLUTIONS FOR THE RBETs-M LEAD–BISMUTH FAST REACTOR
ANALYSIS OF THE POLONIUM HAZARD IN NUCLEAR POWER SYSTEMS WITH LEAD–BISMUTH COOLANT
TESTS OF MODELS OF BREST-OD-300 REACTOR FUEL ELEMENTS IN AN AUTONOMOUS LEAD-COOLED CHANNEL OF A BOR-60 REACTOR
DETERMINATION OF THE FUEL-ASSEMBLY BURNUP IN A RESEARCH REACTOR BY REPEATED SHORT-TIME IRRADIATION FOLLOWED BY γ SPECTROMETRIC MEASUREMENTS
ELECTRONUCLEAR SYSTEMS – A NEW GENERATION OF NUCLEAR POWER SYSTEMS
MEASUREMENT OF THE CHARACTERISTICS OF THE VENTILATION PIPE OF THE FILTRATION SYSTEM FOR THE STEAM-GAS MEDIUM OF A NUCLEAR POWER PLANT
METHOD FOR DETERMINING THE α-RADIOMETRY COEFFICIENTS OF THICK-LAYER PREPARATIONS
EFFECT OF PURGING ON THE TRITIUM CONCENTRATION IN HEAVY-WATER NUCLEAR-REACTOR COOLANT