1. The temperature changes of the fuel, the fuel clad and the reactor building in the event of a break in the hot and cold leg of the VVERl000 power reactors by modeling on the PC TRAN program.
- Author
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Radhi, Ismail Abdulhussein, Al-Bahli, Hamid Moeedi, and Ebrahiem, Sameera Ahmed
- Subjects
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NUCLEAR fuels , *PRESSURIZED water reactors , *FAST reactors , *RADIOACTIVE elements , *NUCLEAR accidents , *POLLUTION , *SYSTEM failures - Abstract
In this paper, the calculation of the fuel temperatures, the fuel clading, and the reactor building will be studied within a time of 300 seconds when fractures of 25,50, 75 and 100 square centimeters occur in both the hot feet and the cold feet, and a comparison between them for the VVER1000 reactor. Since a break in the steam line mainly leads to a loss in the coolant, a break of 100 square centimeters leads to the accident of losing the coolant to a huge break, [ 1 ] which is responsible for many serious nuclear accidents. Simulation results are analyzed to distinguish deviations from normal operating values. The failure of the containment system due to any of these deviations can be verified to foretell any opportunity of contamination seeping into the environment by the radioactive elements. As well as using the correct methods to switch off the reactor and bypass the problem, if any.It is assumed that a fracture occurred at the beginning of the operating time i.e. after 0 seconds. in this study, This was set up to take advantage of the PCTRAN program to obtain the maximum generation of simulation data for accident scenarios to predict fuel temperatures and clading and prevent melting from the watery - watery reactor VVER1000, which is a series of several designs of pressurized water type reactors. It was developed by the Soviet Union, and now Russia by 0KB Gidropress. The generated electrical capacity ranges between 300 thousand megawatts and 1700 thousand megawatts. [ABSTRACT FROM AUTHOR]
- Published
- 2022
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