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The French Nuclear Island Equipment Design and Construction Rules of Association, “PWR Nuclear Island Mechanical Equipment Design and Construction Rules (RCC-M)”, Paris, 2000.

has been cited by the following article:

• TITLE: Stress Analysis for Reactor Coolant Pump Nozzle of Nuclear Reactor Pressure Vessel

  AUTHORS: Lijing Wen, Chao Guo, Tieping Li, Chunming Zhang

  KEYWORDS: Numerical Simulation; Reactor Pressure Vessel; Stress Analysis

  JOURNAL NAME: Journal of Applied Mathematics and Physics, Vol.1 No.6, December 3, 2013

  ABSTRACT: Integrated reactor structural design makes the pressure vessel itself and loads more complicated, so stress concentration makes strength failure easier at reactor coolant pump nozzle. The general purpose finite element program ANSYS/ WORKBENCH was used for 3D stress and fatigue analysis and the results of the evaluation are based on RCC-M criteria. The integrated reactor structural design is evaluated to demonstrate with applicable criteria and ANSYS/WORK- BENCH has better operability than ANSYS APDL on stress analysis of reactor pressure vessel.