Analysis of Manual Reactor Trip of NEK NPP in APROS Computer Code
| Autor: | Tadeja Polach, Dejan Slovenc, Jure Jazbinšek, Ivica Bašić, Luka Štrubelj |
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| Rok vydání: | 2022 |
| Předmět: | |
| Zdroj: | Journal of Energy : Energija Volume 65 Issue 3-4 |
| ISSN: | 1849-0751 0013-7448 |
| DOI: | 10.37798/2016653-4116 |
| Popis: | The Slovenian Krško Nuclear Power Plant (NEK) model was built in using APROS - Advanced PROcess Simulation environment. The basis for the this model was the RELAP5/MOD3.3 Engineering Handbook, the model was updated to the 26th cycle and also includes the upflow conversion modification. A detailed model nodalisation was created for each system and every system was separately validated. The current model covers the primary circuit with the core kinetics model, the secondary circuit and their control systems. The steady state of the APROS NEK model already having been validated, the plan now is to validate the model for some transients and design basis accidents. In this article the plant behaviour after the manual reactor trip is analysed in detail. Two scenarios of the manual reactor trip transient are performed, where either the Main Steam Isolation Valve (MSIV) closes after 60s – case A, or remains open – case B. After the manual reactor trip from the 100% power, the control system signal actuations and their times were followed and then the responses of different affected systems were being observed. All those recorded values were then compared with the identical transient performed on the similar NEK model with the RELAP5/MOD3.3 system code. This procedure allowed to bring the current APROS NEK model one step forward towards being assured to have accurate calculations. |
| Databáze: | OpenAIRE |
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