锻压技术

第三代核电蒸汽发生器管板锻件制造工艺

英文标题：Manufacturing process on tube plate forgings for the third generation nuclear steam generator

作者：张跃王岩张灵宇陈一伟赵立彬

分类号：TG317

出版年,卷(期):页码：2021,46(10):44-48

摘要：

为优化“华龙一号”蒸汽发生器管板锻件制造工艺，并为其他第三代核电容器类锻件的制造工艺提供参考，从冶炼、锻造、热处理、无损检验以及理化检验等主要制造和检验工艺环节，对我国第三代核电机组“华龙一号”蒸汽发生器管板锻件的制造工艺进行了探讨，对各个主要工艺环节的制造和控制要点进行了描述，通过对上述主要工艺环节的控制和优化，最终获得的理化、无损及规格尺寸等各方面的性能指标均满足相关标准和技术条件要求，且获得了性能指标有一定裕量的“华龙一号”蒸汽发生器管板锻件，同时也为其他第三代核电容器类锻件的制造工艺摸索出了一条可行道路。

In order to optimize the manufacturing process of tube plate forgings for “Hualong No.1” steam generator and provide the reference for the manufacturing process of the other third generation nuclear capacitor forgings, based on the main manufacturing and inspection process, such as smelting, forging, heat treatment, nondestructive testing and physical and chemical inspection, the manufacturing process of steam generator tube plate forgings for the third generation nuclear power unit “Hualong No.1” in China was discussed, and the manufacturing and control points of each main process were described. Through the control and optimization of the above main processes, the tube plate forgings of “Hualong No.1” steam generator with the physical and chemical, nondestructive, specification and sizes and other performance indicators that met the requirements of relevant standards and technical conditions and with a certain margin of performance indicators were obtained finally, and at the same time, a feasible way for the manufacturing process of the other third generation nuclear capacitor forgings was also explored.

基金项目：

作者简介：张跃（1981-），男，硕士，高级工程师 E-mail：nsczhangyue@163.com 通信作者：赵立彬（1987-），男，硕士，工程师 E-mail：zhlbhit@126.com

参考文献：

[1]刘锐,李铁萍,褚倩倩,等.核电蒸汽发生器一次侧应力分布研究[J].压力容器,2017,34(1):30-34.

Liu R, Li T P, Chu Q Q, et al. Study on primary side stress distribution of steam generator in nuclear power plant[J]. Pressure Vessel Technology, 2017, 34(1):30-34.

[2]施耀新，田洪志. 反应堆压力容器母材60年寿命性能要求及工艺措施[J]. 发电设备，2012，26(2): 134-137.

Shi Y X, Tian H Z. Property requirements and technological measures of a based metal for reactor pressure vessels with an expected 60-year Life[J]. Power Equipment, 2012, 26(2): 134-137.

[3]杨文斗. 反应堆材料学[M]. 北京: 原子能出版社，2000.

Yang W D. Reactor Materials [M]. Beijing: Atomic Energy Press, 2000.

[4]张跃,向恒,吕艳新,等.ACP1000核反应堆堆芯支承板锻件制造工艺研究[J].热加工工艺,2020,49(17):95-97,100.

Zhang Y, Xiang H, Lyu Y X, et al. Research on manufacturing process of ACP1000 nuclear reactor internal core support forgings[J]. Hot Working Technology, 2020, 49(17):95-97, 100.

[5]张跃,陈一伟,赵立彬,等.ACP1000锻造主泵泵壳制造工艺及质量控制[J].锻压技术,2020,45(9):41-44，50.

Zhang Y, Chen Y W, Zhao L B, et al. Manufacturing process and quality control of forging primary pump casing for ACP1000[J]. Forging & Stamping Technology, 2020, 45(9):41-44, 50.

[6]RCC-M M380, Forging ratio[S].

[7]张文广，李茂林，郭德朋，等. 核电SA508-3钢研究进展[J]. 热加工工艺，2014，43(16): 10-13.

Zhang W G, Li M L, Guo D P, et al. Study on progress of SA508-3 steel for nuclear power[J]. Hot Working Technology, 2014, 43(16): 10-13.

[8]赵品，谢辅洲，孙文山. 材料科学基础[M]. 哈尔滨:哈尔滨工业大学出版社，1999.

Zhao P, Xie F Z, Sun W S. Fundamentals of Materials Science[M]. Haerbin: Harbin Institute of Technology Press, 1999.

[9]迟露鑫，麻永林，邢淑清，等. 核压力容器SA508-3钢高温性能试验分析[J]. 四川大学学报: 工程科学版，2011，43(2): 202-206.

Chi L X, Ma Y L, Xing S Q, et al. Analysis on high temperature performance of SA508-3 steel for nuclear power[J]. Journal of Sichuan University: Engineering Science Edition, 2011, 43(2): 202-206.

[10] RCC-M MC5000, Magnetic particle examination[S].

[11] RCC-M M2115, 18MND5 manganese-nickel-molybdenum alloy steel forgings for PWR steam generator tube plates[S].

[12] GB/T 10561—2005，钢中非金属夹杂物含量的测定标准评级图显微检验图[S].

GB/T 10561—2005, Steel—Determination of content of nonmetallic inclusions—Micrographic method using standards diagrams[S].

服务与反馈：

【文章下载】【加入收藏】