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The analysis of accident scenarios in a nuclear power plant and consequently a review of the proper functioning of safety systems is very importance. In this paper, an analysis of a anticipated transient without scram has been done in the Loss of flow scenario with modeling the VVER-1000 reactor of Bushehr by MELCOR1.8.6 code. The chronological sequence of the different steps and the history of the parameters under this accident calculated with the code are evaluated. Parameters such as temperature and pressure changes in the primary and secondary circuit, temperature changes of fuel and fuel clad are calculated as well as a comparison with the melting temperature. Also, the rate of hydrogen production and pouring molten material into the reactor cavity is calculated. This information is very useful for managing the ATWS accident and controlling the reactor. Also, this results to assess Bushehr nuclear power plant. The results show that thermodynamic parameters of pressure and temperature passes the limit without any accident management.

ATWS severe accident analysis in the loss of flow scenario using the MELCOR code in Bushehr nuclear Power Plant