Abstract
Spills of liquid radioactive material are reviewed as potential event that can be associated with release into the atmosphere. Existing approaches to radiological impact assessment for onsite as well as offsite of facility are presented. The example of using the actual Java version of the European RODOS system as prototype of the decision support system shows the general implementation of the analysis and preparation of initial data in order to model the radiological impact on the public, personnel and environment. Given the specifics of the occurrence of emergency scenarios of this type, features of atmospheric models application, description of the source term model, software integration features, ventilation task solving, completeness and format of the initial data required for radiological consequence modelling.
Highlights
Today, more and more often in order to model the radiological impact on the public, personnel and environment, decision support systems (DSS) for responding to nuclear and radiological accidents in real time are used (RODOS, ARGOS, HPAC, NARAC, etc. [1,2,3,4,5,6])
We focus on the relationship of these pathways and study the process of evaporation as special one for accident with spill of liquid radioactive material (LRM) (Fig. 2)
For the first time source term model for radioactive liquids spills taking into account technological premises and adjacent environmental has been proposed and developed
Summary
More and more often in order to model the radiological impact on the public, personnel and environment, decision support systems (DSS) for responding to nuclear and radiological accidents in real time are used (RODOS, ARGOS, HPAC, NARAC, etc. [1,2,3,4,5,6]). In addition to the primary tasks of the software, they are applied in frame of emergency preparedness and planning, quantitative and qualitative analysis of possible scenarios taking into account the evolution and phenomenological stages of the events. This is primarily due to the wide range of data assessment tools both in terms of design capacity and in terms of simplicity of input and analysis of results. The wide variety of potential emergency processes at nuclear power plants does not allow to create unified tool for preparing source term data that would cover all possible state of the affected facility. According to study [2, 3], these codes have some disadvantages and often require a large amount of input data, calculation time
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