Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering

Dongxu Du, D. Zhao, Liguo Ren, Wenhui Zhang, Jiaju Li, Xi-kou He
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Abstract

Due to low hardenability, the conventional SA508Gr.3 steel cannot meet the design requirements of increasing wall thickness of forgings for nuclear power pressure equipment. In this paper, the hot processing and manufacturing technology of SA508Gr.4N steel ultra-thick forgings for the new generation of nuclear reactor pressure vessel was introduced. The engineering development of nuclear SA508Gr.4N steel forgings with wall thickness from about 700mm to 1000mm was realized by China First Heavy Industry (CFHI). The largest forging was made of 228 tons ingot and the final maximum dimensions reached about ϕ4000mm × 1000mm. The samples were taken anatomically from the forging at various thickness and radial positions, and subjected to the tensile, Charpy impact and Drop-weight tests. As a result, the full-section property of the forging met the requirements of the ASME code. Compared with nuclear SA508Gr.3 steel forgings, the strength and toughness of SA508Gr.4N forgings were greatly improved. Meanwhile, based on the fact that the actual property value is much higher than the requirements of ASME code, higher design property requirements of SA508Gr.4N steel forging was proposed. In addition, the nuclear neutron-irradiation-embrittlement data of SA508Gr.4N steel, which were cut from the actual engineering forgings and experimented in a high flux engineering test reactor (HFETR), was obtained. The main research and development goals for engineering application of SA508Gr.4N steel in the future were also discussed.
SA508Gr的研发核工程用高强度高韧性4N钢超厚锻件
由于淬透性低,传统的SA508Gr。3 .钢不能满足核电压力设备锻件增壁厚的设计要求。本文对SA508Gr的热加工制造工艺进行了研究。介绍了新一代核反应堆压力容器用4N钢超厚锻件。核能SA508Gr的工程开发。4N钢锻件的壁厚从700mm到1000mm左右由中国第一重工(CFHI)实现。最大锻件为228吨铸锭,最终最大尺寸约为4000mm × 1000mm。从不同厚度和径向位置的锻件上解剖取样,并进行拉伸、夏比冲击和落锤试验。结果表明,锻件的全截面性能满足ASME规范的要求。与核SA508Gr相比。3 .钢锻件,强度和韧性均达到SA508Gr。4N锻件得到了很大的改进。同时,基于实际性能值远高于ASME规范的要求,SA508Gr的设计性能要求较高。提出了4N钢锻件。此外,SA508Gr的核中子辐照脆化数据。在高通量工程试验堆(HFETR)上获得了从实际工程锻件中切割出来的4N钢。SA508Gr的主要研发目标是工程应用。并对4N钢的发展前景进行了探讨。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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