Conference Proceedings Paper
Thermalhydraulic System Analysis Using the MARS Code for the Transient Steam Generator Tube Rupture Accident
NURETH-14 - 2011 September 25-30
Kyoung-Ho Kang (Korea Atomic Energy Research Institute)
Seung-Wook Lee (Korea Atomic Energy Research Institute)
Sung-Won Bae (Korea Atomic Energy Research Institute)
Won-Pil Baek (Korea Atomic Energy Research Institute)
Ki-Yong Choi (Korea Atomic Energy Research Institute)
A postulated SGTR accident of the APR1400 was analysed using the best estimate safety analysis code, MARS. The main objective of this study is not only to provide physical insight into the system response of the APR1400 reactor during a SGTR but also to investigate the effect of reactor trip type of a HSGL and a LPP on the thermal-hydraulic system response. As for the tube rupture modelling method, double tube modelling was adopted. Broken U-tubes were modelled as a separate assembly of a single volume. The reactor trip type affected the overall progress of the major events. However, the effect on the thermal-hydraulic response of the plant was trivial.
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