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

IF 2.7 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2025-03-01 Epub Date: 2025-01-11 DOI:10.1016/j.nme.2025.101873
Christoph Bläsius , Jürgen Sievers , Yongjian Gao , Stefan Weihe
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Abstract

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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低合金反应堆压力边界钢在严重事故载荷范围内的行为及其对有限元分析中材料建模的影响
本文对低合金反应堆压力边界钢(包括SA533B1、SA508 Gr.3、16MND5、20 MnMoNi 5.5、19MnNiMo、22 NiMoCr 37、15Kh2MFA和15Kh2NMFA)在严重事故载荷范围内的行为进行了全面的材料数据和知识汇编。这些数据是在最近完成的OECD/NEA CSNI WGIAGE/WGAMA关于RPV在船内滞留完整性评估状态报告的活动范围内编制的,包括最近不同测试活动的新结果。对数据进行比较和解释,揭示极端载荷范围内的特殊性,例如短期蠕变和拉伸变形之间的关系,以及钢等级之间的相似性。识别了影响变形、损伤和破坏行为的相关因素,并对潜在的散射和不确定性来源进行了讨论和量化。这些数据证实了这样的假设,即由于高延性,在相应的加载范围内,外截面的损失是破坏和破坏的主要机制。在此基础上,提出了有限元规范中材料建模的启示,并提出了最佳实践。这些包括经典模型和本构模型之间的选择,变形规律的选择,对初级,次级和/或三级蠕变的考虑,潜在的陷阱以及为相关破坏机制选择合适的破坏准则。
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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