Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Analysis of control rod driving mechanism nozzle rupture with loss of safety injection at the ATLAS experimental facility using MARS-KS and TRACE

  • Hyunjoon Jeong (Department of Safety Engineering, Incheon National University) ;
  • Taewan Kim (Department of Safety Engineering, Incheon National University)
  • Received : 2023.09.13
  • Accepted : 2024.01.06
  • Published : 2024.06.25
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Abstract

Korea Atomic Energy Research Institute (KAERI) has operated an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), with reference to the APR1400 (Advanced Power Reactor 1400) for tests for transient and design basis accidents simulation. A test for a loss of coolant accident (LOCA) at the top of the reactor pressure vessel (RPV) had been conducted at ATLAS to address the impact of the loss of safety injections (LSI) and to evaluate accident management (AM) actions during the postulated accident. The experimental data has been utilized to validate system analysis codes within a framework of the domestic standard problem program organized by KAERI in collaboration with Korea Institute of Nuclear Safety. In this study, the test has been analyzed by using thermal-hydraulic system analysis codes, MARS-KS 1.5 and TRACE 5.0 Patch 6, and a comparative analysis with experimental and calculation results has been performed. The main objective of this study is the investigation of the thermal-hydraulic phenomena during a small break LOCA at the RPV upper head with the LSI as well as the predictability of the system analysis codes after the AM actions during the test. The results from both codes reveal that overall physical behaviors during the accident are predicted by the codes, appropriately, including the excursion of the peak cladding temperature because of the LSI. It is also confirmed that the core integrity is maintained with the proposed AM action. Considering the break location, a sensitivity analysis for the nodalization of the upper head has been conducted. The sensitivity analysis indicates that the nodalization gave a significant impact on the analysis result. The result emphasizes the importance of the nodalization which should be performed with a consideration of the physical phenomena occurs during the transient.

Keywords

Acknowledgement

This work was performed within the program of the 6th ATLAS Domestic Standard Problem (DSP-06), which was organized by the Korea Atomic Energy Research Institute (KAERI) in collaboration with Korea Institute of Nuclear Safety (KINS) under the National Nuclear R&D Program (NRF-2017M2A8A4015028) funded by the Ministry of Education, Science and Technology (MEST) of the Korean government. The authors are as well grateful to the 6th ATLAS DSP program for providing the opportunity to publish the results. This work was financially supported by Incheon National University Research Grant in 2021 (No. 2021-0112).

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