Abstract
This report focuses on assessment of radiation consequences of releases in accidents with spills of liquid radioactive materials in areas with forced ventilation. During the study, characteristic dependences between parameters of liquid radioactive materials and air exchange in areas with forced ventilation and associated radiation consequences were determined. The proposed approach is based on the theory of non-stationary heat and mass transfer in surface evaporation of liquid heated below the boiling temperature. The physical model includes: liquid radioactive material, steam-aerosol radioactive mixture, air of forced ventilation, airborne filters, and floor of the emergency area. The key aspects of the model are evaporation of liquid material, its removal with exhaust ventilation and partial trapping on airborne filters. It is considered that the steam-aerosol radioactive mixture is released to the environment after filters. The advantage of this model is the possibility to determine integral release of radionuclides to the environment and activity concentration of air in the emergency area at any moment after beginning of the accident, effective dose received by an adult during 14 days for a wide range of input thermodynamic and geometrical parameters, different operating modes of the ventilation system and different productivities of the filtering system. Results from assessment of radiation consequences for the selected accident are presented and the associated effect of filtering systems is analyzed.
Highlights
Nowadays, one of the priorities in nuclear industry is to minimize actual radiation exposure on the population during normal operation of the facilities as well as potential one in case accidents
This work is devoted to the class of accidents involving spills of liquid radioactive materials (LRM) in areas with forced ventilation, assessment of activity and power of releases as well as assessment of the radiation consequences of such releases
The main sources of LRM at nuclear power plants and nuclear complexes are as follows: primary coolant that is discharged for operational reasons; water that is used to back flush filters and ion exchangers; Evaluation of Radiation Consequences of Releases in Accidents with Spills of Liquid
Summary
One of the priorities in nuclear industry is to minimize actual radiation exposure on the population during normal operation of the facilities as well as potential one in case accidents. In case of an accident, the minimization is based on the dependence of radiation consequences on parameters that caused them. Worldwide there have been more than 22 significant accidents with spills of liquid radioactive materials at nuclear fuel cycle facilities for the last 60 years according to KPI’s conference proceedings [1]. Many special computer codes and methods are currently developed to assess, with sufficient accuracy, parameters of releases for various accidents at nuclear fuel cycle facilities (e.g. MELCOR computer code manual, US NRC [2] for NPP). These codes often require a large amount of input data and calculation time. The advantage of the approach developed in this paper is rapid assessment of radiation consequences
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