Nuclear and Radiation Safety Journal
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2021

Potential iodine compounds in the BREST-OD-300 reactor lead coolant

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

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

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

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

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

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 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 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

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”

Ensuring radiation safety during decommissioning of nuclear radiation hazardous facilities JSC “VNIINM”

Irradiation embrittlement of RPV steels irradiated by high neutron fluence

Irradiation embrittlement of RPV steels irradiated by high neutron fluence

Methodology for quantitative comparison of different nuclear fuel cycles by their safety

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 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

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

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

Selection of optimal option for radioactive waste management using mathematical methods

The analysis of chemical-technological processes scale factorfor fuel cycle facilities explosion indexes

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 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

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

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

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 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

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