Medical Radiology and Radiation Safety. 2018. Vol. 63. No. 6. P. 27–33

RADIATION SAFETY

DOI: 10.12737/article_5c0c15499e8d84.42337847

B.A. Galushkin¹, S.V. Gorbunov², V.N. Klochkov¹, V.I. Rubtsov¹, A.A. Molokanov¹

Methodical Apparatus for the Development of Typical Scenarios of Beyond Design Basis Accidents with VVER Reactors in the Planning and Implementation of Protective Measures for the Population

1. A.I. Burnasyan Federal Medical Biophysical Center, Moscow, Russia. E-mail: This email address is being protected from spambots. You need JavaScript enabled to view it. ;
2. All-Russian Research Institute of Ministry of Russian Federation for Civil Defense, Emergency and Elimination of Consequences of Natural Disasters, Moscow, Russia

B.A. Galushkin – Leading Researcher, Dr. Sci. Tech.; S.V. Gorbunov – Chief Researcher, Dr. Sci. Tech.;
V.N. Klochkov – Leading Researcher, Dr. Sci. Tech.; V.I. Rubtsov – Head of Lab., Dr. Sci. Tech.;
A.A. Molokanov – Leading Researcher, PhD Tech.

Abstract

Purpose: To develop a simple methodological apparatus for constructing typical scenarios of accidents and estimate of emissions of radioactive substances from nuclear power plants with VVER reactors in the planning and implementation of protective measures for the population.

Material and methods: To build the model of release of radionuclides into the environment in case of an accident used literary experimental data of outputs of the radioactive substances from the fuel when it is heating and melting, the destruction of the fuel rod cladding, the use of technical means retention of radioactive substances in the containment of the reactor and their behaviour in the containment (sedimentation, sorption, etc.).

Results: Mathematical apparatus has been developed to quantify the magnitude of emissions of radioactive substances at nuclear power plants with VVER reactors depending on the time for dose-forming radionuclides in the instantaneous rupture of cooling pipelines in the presence of additional failure of NPP safety systems. The amount of emission of each deterministic of an accident correspond to the level 4 to 7 of the INES scale. Radionuclide release into the environment was calculated in the following physical and chemical processes: heating and melting of fuel, depressurization of fuel rod claddings, peculiarities of the behavior of radionuclides in the containment shell (deposition, etc.) and operation of technical means to ensure radiation safety, structural leakages of the buildings. As an example, the assessment of the release of radionuclides into the environment depending on the time for level 5 of the INES accident scale is given.

Conclusion: Methodical apparatus can be used in the construction of typical scenarios for the development of basis accidents and assessment of radioactive emissions at nuclear power plants with VVER reactors in the planning and implementation of protective measures for the population and emergency exercises and training.

Key words: radiation accidents, radionuclides, VVER reactors, scenarios, nuclear fuel element, temperature, melting, emission

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For citation: Galushkin BA, Gorbunov SV, Klochkov VN, Rubtsov VI, Molokanov AA. Methodical Apparatus for the Development of Typical Scenarios of Beyond Design Basis Accidents with VVER Reactors in the Planning and Implementation of Protective Measures for the Population. Medical Radiology and Radiation Safety. 2018;63(6):27-33. Russian.

DOI: 10.12737/article_5c0c15499e8d84.42337847

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