Study on the Influence of Reactor System LOCA Modeling Mode on Dynamic Analysis

Author:

Shuai Liu,Xuan Huang,Zhipeng Feng,Zhongxiu Zeng,Huanhuan Qi,Xiaozhou Jiang

Publisher

Springer Nature Singapore

Reference5 articles.

1. Hermansky, P., Krajcovic, M.: The numerical simulation of the WWER440/V213 reactor pressure vessel internals response to maximum hypothetical large-break loss of coolant accident. Nucl. Eng. Des. 241(4), 131–137 (2011)

2. Qing, M.: Nonlinear dynamic analysis under LOCA condition for reactor system. Nucl. Power Eng., 8 (1999)

3. Huanhuan, Q., Wanjun, W., Pingchuan, S. et al.: Dynamic analysis of fuel assembly for accident condition based on ANSYS. Nucl. Power Eng., 6 (2018)

4. Qian, H., Xiaofei, Y., Huanhuan, Q. et al.: Numerical analysis of dynamic response for SG LOCA shaking. Nucl. Power Eng., 2 (2019)

5. USNRC, SRP 3.7.2 Rev. 3, Seismic system analysis 3 (2003)

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