摘要
ASME规范第Ⅲ卷第5册(简称ASME-Ⅲ-5)提供了核1级部件在高温下使用的设计分析方法和评定准则。本文对高温的定义进行简介,对ASME规范核1级部件在高温下考虑的设计载荷、失效机制、设计分析方法以及评定准则的特点进行总体介绍。通过对ASME规范与其他高温规范R5、RCC-MRx、MONJU在基于损伤模式下的载荷控制应力限制和变形控制限制的分析方法及准则进行对比,探究ASME规范在分析方法准则中的优势与局限性,得出ASME规范传统采用的基于应力分类的弹性分析法表现优异,但由于本身固有特性并不能完美解决规范所含括的各个失效机制的结论,提出若干项改进ASME-Ⅲ-5高温1级部件设计规范的方法。本文指出的ASME-Ⅲ-5可改进方向可进一步提高规范发展使用的先进性、经济性和安全性,同时对开发构建我国自主化的核承压高温使用1级部件设计规范具有指导作用。
Division 5 of the ASME code sectionⅢ(referred to as ASME-Ⅲ-5)provides design-by-analysis methods and evaluation criteria for Class 1 nuclear components working at high temperatures.It has a long history and is the main international design code for high temperature nuclear equipment.It took the lead in adopting the idea of stress classification and first introduced the concepts of primary stress,secondary stress and peak stress,which had a far-reaching impact on the development of subsequent other high temperature design codes.However,with the rapid development of computational methods,high-performance computer technology,commercial finite element software and high temperature inelastic analysis methods,the results derived from elastic analysis and the evaluation of stress classification used by ASME as a mainstream method exist the limitation of overly conservatism and thus insufficient design economy.This paper first introduced the definition of high temperature condition and the insignificant creep temperature,as well as the design loads,failure mechanisms,design-by-analysis methods,and evaluation criteria of ASME code for nuclear Class 1 components at high temperature.Then,by comparing the analysis methods and criteria of primary load limit and deformation control limit of ASME with other high temperature codes,such as R5,RCC-MRx and MONJU(with or without consideration of the time dependence of creep),the advantages and limitations of ASME analysis methods and criteria were explored.Each code has its distinct characteristic.British R5 code focuses on the reference stress method and the application of limit analysis.French RCC-MRx code is in the same lineage with ASME,but distinguishes between significant/insignificant creep and significant/insignificant irradiation effects.Japanese MONJU code distinguishes the long-term load from short-term load,such as seismic load.Long-term loads and short-term loads adopt different limits to avoid overly conservatism.It is concluded that the elastic analysis based on t
作者
刘正奇
高付海
LIU Zhengqi;GAO Fuhai(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2024年第4期848-855,共8页
Atomic Energy Science and Technology
