Influence of main variables modifications on accident transient based on AP1000-like MELCOR model

7th European Thermal-Sciences Conference

Malicki, M.^1 ; Piekowski, L.^1

AGH University of Science and Technology, Faculty of Energy and Fuels, Mickiewicza 30, Krakow

30-059, Poland^1

关键词: Generic modeling;    Nuclear safety;    Primary reactor;    Reactor designs;    Safety level;    Severe accident;    Small modular reactors;    System codes;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/745/3/032010/pdf
DOI  :  10.1088/1742-6596/745/3/032010

来源: IOP

【 摘 要 】

Analysis of Severe Accidents (SA) is one of the most important parts of nuclear safety researches. MELCOR is a validated system code for severe accident analysis and as such it was used to obtain presented results. Analysed AP1000 model is based on publicly available data only. Sensitivity analysis was done for the main variables of primary reactor coolant system to find their influence on accident transient. This kind of analysis helps to find weak points of reactor design and the model itself. Performed analysis is a base for creation of Small Modular Reactor (SMR) generic model which will be the next step of the investigation aiming to estimate safety level of different reactors. Results clearly help to establish a range of boundary conditions for main the variables in future SMR model.