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核电项目堆内构件用SA479 S21800材料性能研究

Study on characteristics of SA479 S21800 materials for reactor internals of nuclearpower project
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摘要 某核电项目堆内构件用SA479 S21800奥氏体不锈钢棒材,在ASME II材料篇的基础上增加了350℃高温拉伸要求,致使该材料的制造难度大大增加。尤其针对规格大于Φ150 mm棒材,技术要求拉伸试样横向取样,高温抗拉强度很难满足大于或等于535 MPa的要求。为了满足项目应用要求,本文将研究规格大于Φ150 mm的SA479 S21800奥氏体不锈钢棒材性能特点,通过改进锻造工艺,优化钢锭化学成分含量,提升棒材力学性能。最终为大规格SA479 S21800材料的生产提供有效的指导。 The austenitic stainless steel(SA479 S21800)bar for reactor internals of a nuclearpower project has added 350℃high temperature tensile requirements on the basis of ASME II materials,which greatly increases the manufacturing difficulty of this material.Especially,the technical requirements require transverse sampling of tensile samples,it is difficult to meet the high temperature tensile strength greater than or equal to 535Mpa for specifications greater than 150mm.In order to meet the project application requirements,this paper will study the characteristics of S479 S21800 for specifications greater than 150mm.The mechanical properties of the material are improved by improving the forging process and optimizing the chemical composition content of the ingot.Finally,this paper provides effective guidance for the production of large-scale SA479 S21800 materials.
作者 万积俊 WAN Jijun(Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233,China)
出处 《四川冶金》 CAS 2022年第2期19-22,43,共5页 Sichuan Metallurgy
关键词 核电 SA479 S21800 堆内构件 锻造工艺 奥氏体不锈钢 nuclear power SA479 S21800 reactor internals forging process austenitic stainless steel
作者简介 万积俊(1989-),男,硕士研究生,主要从事核电设备和材料供应商制造工艺流程、制造质量和质量体系等的监督管理工作,E-mail:vanjunhust@163.com。
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