Journal of the Korean Society of Safety (한국안전학회지)

The Korean Society of Safety (한국안전학회)
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Evaluation of SPACE Code Prediction Capability for CEDM Nozzle Break Experiment with Safety Injection Failure

안전주입 실패를 동반한 제어봉구동장치 관통부 파단 사고 실험 기반 국내 안전해석코드 SPACE 예측 능력 평가

  • Nam, Kyung Ho (Korea Hydro & Nuclear Power Co., Ltd. Central Research Institute)
  • 남경호 (한국수력원자력(주) 중앙연구원)
  • Received : 2022.08.17
  • Accepted : 2022.10.12
  • Published : 2022.10.31
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Abstract

The Korean nuclear industry had developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code, which adopts a two-fluid, three-field model that is comprised of gas, continuous liquid and droplet fields and has the capability to simulate three-dimensional models. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for the accident management plan of a nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification is required for the separate and integral effect experiments. Therefore, the goal of this work is to verify the calculation capability of the SPACE code for multiple failure accidents. For this purpose, an experiment was conducted to simulate a Control Element Drive Mechanism (CEDM) break with a safety injection failure using the ATLAS test facility, which is operated by Korea Atomic Energy Research Institute (KAERI). This experiment focused on the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The results of the overall system transient response using the SPACE code showed similar trends with the experimental results for parameters such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it can be concluded that the SPACE code has sufficient capability to simulate a CEDM break with a safety injection failure accident.

Keywords

Acknowledgement

This work was performed within the program of the sixth ATLAS Domestic Standard Problem (DSP-06), which was organized by Korea Atomic Energy Research Institute (KAERI) in collaboration with the Korea Institute of Nuclear Safety (KINS) under the national nuclear R&D program funded by the Ministry of Education (MOE) of the Korean government. The authors are also grateful to the sixth ATLAS DSP-06 program participant: KAERI for the experimental data and to the council of the sixth DSP-06 program for providing the opportunity to publish the results.

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