After Fukushima Daiichi Accident, many passive systems have been investigated to enhance the safety of nuclear power plant. Currently APR-1400 has a turbine-driven and motor-driven auxiliary feed water system (AFWS) for the secondary side heat removal system. Even though those systems provide long coping time but still rely on power source. Thus, Passive auxiliary feed water system (PAFS) has been developed to replace the AFWS as it is expected to increases the safety of the plant. Therefore, KAERI the operating agent of ATLAS project included accident scenarios related to PAFS as one of their topics. For this study, ATLAS B1.1 test was selected to analyze 2-inches cold leg break accident scenario with the operation of PAFS using two thermal hydraulic codes which are RELAP5 and TRACE. the steady-state input file was generated as well as transient input file. It was found that, RELAP5 steady-state and transient results are close to experimental data but with higher transient break flow in simulation. Also, the events in experiment occurred earlier than simulation except in initiation of PAFS, safety injection tanks operation and accident mitigation action. However, only steady-state condition was determined by TRACE code. The steady-state results showed closer trend to experiment than RELAP5.
| Date of Award | Dec 2022 |
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| Original language | American English |
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| Supervisor | Ahmed Alkaabi (Supervisor) |
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- PAFS
- RELAP5
- TRACE
- ATLAS B1.1 test
- Steady-state results
Accident Analysis of 2 Inches Cold Leg Break with the Passive Auxiliary Feed-Water System via OECD-ATLAS Project
Mohammed Bin Khaif, A. (Author). Dec 2022
Student thesis: Master's Thesis