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Application of RELAP5-MV for some accident scenarios analysis of AP1000   YOUSIF Eltayeb1,*, ZHANG Zhijian1, TIAN Zhaofei1, JU Haoran1,and WANG Yafeng1     1. Harbin Engineering University, 145 Nantong Street, Harbin, Heilongjiang, China, 150001 (eltayeb2003@gmail.com)   Abstract: RELAP5 code developed in U.S.A. to predict the accident behaviour of light water reactor is widely used around the world. On the other hand the RELAP5-MV had been developed by the authors of this paper to improve the input preparation functions of the RELAP5 to help users of RELAP5 for fast modeling the plant system to conduct simulation practice by advanced graphics displays. However, it is needed to validate the help functions of the RELAP-MV for users by testing different accident scenarios in actual plant conditions. Accuracy and reliability of RELAP5-MV have been confirmed by simulating small break loss of coolant accident (SBLOCA) and steam generator tube rupture (SGTR) accident in AP1000. The results obtained by RELAP5 and RELAP5-MV are in good agreement as they are based on the same models of light water reactor accident analysis. But in comparison with RELAP5, RELAP5-MV resulted in making simulation of nuclear power systems easier and more convenient than RELAP5 for users especially the beginners. With RELAP5-MV the simulation process is simplified and simulation efficiency is increased. By both component and modular modeling methods supported in RELAP5-MV. In this paper, the predicted plant behaviour of the AP1000 by using RELAP5-MV is presented for SBLOCA and SGTR scenarios. The results obtained by RELAP5-MV have demonstrated the effectiveness of RELAP5-MV for such transients and accident scenarios simulations. Keywords: RELAP5;loss of coolant accident; SGTR; AP1000;graphical modeling
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