WANG Jun-wei, ZHANG Zhou-hong, WU Gao-feng, FAN Li-ming. Reactor Vessel Stress Analysis for CPR1000 Nuclear Power Plant[J]. Atomic Energy Science and Technology, 2008, 42(增刊2): 495-499. DOI: 10.7538/yzk.2008.42.suppl2.0495
Citation: WANG Jun-wei, ZHANG Zhou-hong, WU Gao-feng, FAN Li-ming. Reactor Vessel Stress Analysis for CPR1000 Nuclear Power Plant[J]. Atomic Energy Science and Technology, 2008, 42(增刊2): 495-499. DOI: 10.7538/yzk.2008.42.suppl2.0495

Reactor Vessel Stress Analysis for CPR1000 Nuclear Power Plant

  • The reactor vessel is an important safeguard for nuclear safe, it must insure that the reactor vessel as a pressure vessel meets the requirements of the RCC-M code by stress analysis. First, 3D model of the reactor vessel is built with ANSYS which is a finite element analysis software. Then, the stress intensities of the reactor vessel effected by different pressure, temperature, earthquake and other loads were computed. Last, the result with limits applicable showed in RCC-M was compared. This report shows that the reactor vessel meets the requirements of the RCC-M code under calculated condition and shows a good way for primary equipments stress analysis.
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