Nuclear and Radiation Safety Journal
ISSN: 2218-8665 (print), 2218-869X (online)
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2021
Potential iodine compounds in the BREST-OD-300 reactor lead coolant
Potentially explosive mixtures “organic component–nitric acid–water” during evaporation at nuclear fuel cycle facilities
Some aspects of insuring radiation safety during the temporary storage of radioactive waste in non-returnable protective containers in light hangar-type storage facilities
The graphic approach to justification of high-level waste vitrification in cold crucible induction melter
Use of the VVER simulator in SEC NRS for the support of expert review of beyond-design-basis accident management procedures
2020
A system of organizational and technical measures for safe closure of deep disposal facilities for liquid radioactive waste. Conceptual provisions
Development and application of nondestructive measurements of nuclear materials in depositions, aggregations and wastes
Development of legal and regulatory basis for approaches to return of reprocessing products of spent nuclear fuel to the supplier’s state
Development of methodology for primary circuit pressure calculations in case of large break loss of coolant accident in models for rapid assessment for information analytical center of Rostechnadzor
Ensuring radiation safety during decommissioning of nuclear radiation hazardous facilities JSC “VNIINM”
Irradiation embrittlement of RPV steels irradiated by high neutron fluence
Methodology for quantitative comparison of different nuclear fuel cycles by their safety
On limiting radioactive discharges which arise from activities of industrial facilities not utilizing atomic energy
On the evaluation of absorbed dose in vitrified high level radioactive waste with the account of real can geometry
Overview of the IAEA safety standards «Regulations for the safe transport of radioactive material» SSR-6
Selection of optimal option for radioactive waste management using mathematical methods
The analysis of chemical-technological processes scale factorfor fuel cycle facilities explosion indexes
2019
Analysis axial fuel burnup irregularity to VVER-1000 assemblies on low power levels operating
Analysis of recommendations of closing relations used in calculating friction pressure losses in circuits with the natural circulation of two-phase flows of a water-cooled nuclear power unit
Benchmark calculation on reactivity compensation initiated by dilution of boron acid in VVER-1000 primary circuit coolant by stepwise control rods group insertion
On methods for selection of radioactive airborne discharge sources and radionuclides for which discharge limits shall be set
Radiation safety assessment requires correct epidemiological data
Radiation safety studies of fresh fuel handling at increased content of even uranium isotopes in the raw material on RBMK-1000 nuclear power plants
Radiation safety studies of fresh fuel handling at increased content of even uranium isotopes in the raw material on RBMK-1000 nuclear power plants
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