Behavior of low alloy reactor pressure boundary steels in the loading range relevant for severe accidents and implications for material modeling in FE analyses

材料科学 合金 冶金 航程(航空) 核工程 合金钢 反应堆压力容器 复合材料 工程类
作者
Christoph Bläsius,J. Sievers,Yongjian Gao,Stefan Weihe
出处
期刊:Nuclear materials and energy [Elsevier BV]
卷期号:42: 101873-101873 被引量:1
标识
DOI:10.1016/j.nme.2025.101873
摘要

This work presents a comprehensive compilation of material data and knowledge on the behavior of low alloy reactor pressure boundary steels, including SA533B1, SA508 Gr.3, 16MND5, 20 MnMoNi 5 5, 19MnNiMo, 22 NiMoCr 3 7, 15Kh2MFA and 15Kh2NMFA in the severe accident loading range. These data were compiled within the scope of the recently finished OECD/NEA CSNI WGIAGE/WGAMA activity on a Status Report on the RPV Integrity Assessment for In-Vessel Retention and include new results from different recent test campaigns. The data is compared and interpreted, revealing particularities in the extreme loading range, such as a relation between short-term creep and tensile deformation, as well as similarities between steel grades. Relevant factors of influence on deformation, damage and failure behavior are identified, and potential sources of scatter and uncertainties are discussed and quantified. The data confirm the assumption that loss of external cross-section is a principal mechanism of damage and failure in the relevant loading range due to the high ductility. Based on the findings, implications about material modeling in Finite Element codes are drawn and best practices are proposed. These include the choice between classical and constitutive models, the choice of deformation laws, the consideration of primary, secondary and/or tertiary creep, potential pitfalls as well as the selection of suitable failure criteria for relevant failure mechanisms.

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