Fatigue Verification of Class 1 Nuclear Power Piping According to ASME BPV Code  

作　　者：Lingfu Zeng Lennart G. Jansson Lars Dahlstrom 

机构地区：[1]Nuclear Technology, AF-Industry AB, Goteborg SE-401 51, Sweden [2]Technical Analysis, AF-Industry AB, Goteborg SE-401 51, Sweden

出　　处：《Journal of Energy and Power Engineering》2012年第4期519-529,共11页能源与动力工程（美国大卫英文）

摘　　要：In this paper, fatigue verification of Class 1 nuclear power piping according to ASME Boiler ＆ Pressure Vessel Code, Section III, NB-3600, is addressed. Basic design requirements and relevant verification procedures using Design-By-Analysis are first reviewed in detail. Thereafter, a so-called simplified elastic-plastic discontinuity analysis for further verification when the basic requirements found unsatisfactory is examined and discussed. In addition, necessary computational procedures for evaluating alternating stress intensities and cumulative damage factors are studied in detail. The authors＇ emphasis is placed on alternative verification procedures, which do not violate the general design principles upon which the code is built, for further verification if unsatisfactory results are found in the simplified elastic-plastic analysis. An alternative which employs a non-linear finite element computation and a refined numerical approach for re-evaluating the cumulative damage factors is suggested. Using this alternative, unavoidable plastic strains can be correctly taken into account in a computationally affordable way, and the reliability of the verification will not be affected by uncertainties introduced in the simplified elastic-plastic analysis through the penalty factor Ke and other simplifications.

关 键 词：Nuclear power PIPING low-cycle fatigue ASME BPV code alternative rule finite element cyclic plasticity. 

分 类 号：O346.2[理学—固体力学] TH49-65[理学—力学]