BWRX-300 Isolation Condenser System analysis
Pomogaev, Aleksandr (2022)
Diplomityö
2022
School of Energy Systems, Energiatekniikka
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Julkaisun pysyvä osoite on
https://urn.fi/URN:NBN:fi-fe2022100360815
https://urn.fi/URN:NBN:fi-fe2022100360815
Tiivistelmä
The purpose of this master's thesis is to gain an understanding of both the basic principles of modern passive safety systems in the nuclear power industry and to study in depth the individual aspects of the impact on reactor performance in order to take them into account in the design and construction with all safety standards in consideration. Namely, which parameters that can be affected by the safety system under consideration make the greatest contribution to the change in the overall reactor core reactivity.
This paper considers a passive safety system such as the Isolation Condenser System, which is designed for use in conjunction with the current BWRX-300 reactor design.
The work consists of a descriptive part to understand the classification of passive safety systems and the principles of ICS operation in relation to the BWRX-300 reactor design, and a computational part in which the structural and physical parameters of ICS and the reactor core are evaluated, based on reference information from available sources, as well as in the course of mathematical calculations. The whole system is modelled using the TRACE thermohydraulic system code. The purpose of the simulation is to generate reactor core coolant and fuel characteristic curves to calculate the reactivity jump when the passive safety system is activated.
The calculations show that this reactivity jump is acceptable and can be compensated by control rods or other safety systems directly or indirectly affecting the overall reactivity, which confirms the profitability of this type of system and the relevance of industry development in this direction.
This paper considers a passive safety system such as the Isolation Condenser System, which is designed for use in conjunction with the current BWRX-300 reactor design.
The work consists of a descriptive part to understand the classification of passive safety systems and the principles of ICS operation in relation to the BWRX-300 reactor design, and a computational part in which the structural and physical parameters of ICS and the reactor core are evaluated, based on reference information from available sources, as well as in the course of mathematical calculations. The whole system is modelled using the TRACE thermohydraulic system code. The purpose of the simulation is to generate reactor core coolant and fuel characteristic curves to calculate the reactivity jump when the passive safety system is activated.
The calculations show that this reactivity jump is acceptable and can be compensated by control rods or other safety systems directly or indirectly affecting the overall reactivity, which confirms the profitability of this type of system and the relevance of industry development in this direction.