Session: DA-04-01 Inelastic, Nonlinear, and Limit Load Analysis

Paper Number: 62035

Start Time: Tuesday, July 13, 2021, 08:00 PM

62035 - Comparative Research on Nonlinear Analysis Method Technique for the Failure Modes Based on RCC-M Annex ZC 

In the evaluation of nuclear equipment, if the elastic analysis can not meet the corresponding design criteria, the nonlinear analysis method should be adopted to assess the safety of equipment. A new non-linear calculations appendix is supplied in RCC-M 2017 edition annex ZC to secure the nonlinear F.E. calculation performance.

In this paper, the failure modes of nuclear engineering structure are discussed. In order to ensure the safe operation of the structure, the corresponding evaluation criteria formulated by RCC-M code are proposed. Based on the annex ZC of RCC-M 2017 edition, three kinds of nonlinear analysis methods, including limit analysis, plastic analysis and cycle analysis, are studied. A austenitic stainless steel typical nozzle model is used to carry out the finite element calculation. The effect on the limit load is compared between the limit load method of perfect elastoplastic analysis and the secant method of the elastoplastic analysis. The influence of the strain range method and the modified Ke method on the fatigue calculation results is also discussed. The strain range can be determined by monotonic calculation or cyclic calculation. The two kinds of approach is compared in the elastic plastic fatigue calculation. The results show that the fatigue usage gotten by the strain range method is lower than the one by the modified Ke method obviously. There are some uncertain factors in the use of secant method to be discussed.

Presenting Author: Xuejiao Shao Nuclear Power Institute of China

Authors:

Xuejiao Shao Nuclear Power Institute of China
Xiaolong Fu Nuclear Power Institute of China
Hai Xie Nuclear Power Institute of China
Ying Zhang Nuclear Power Institute of China
Jun Tian Nuclear Power Institute of China
Furui Xiong Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China
Mingda Yu Nuclear Power Institute of China
Kaikai Shi Nuclear Power Institute of China