锻压技术

ACP1000锻造主泵泵壳制造工艺及质量控制

英文标题：Forging process and quality control on primary pump casing for ACP1000

作者：张跃陈一伟赵立彬卫东李海涛

分类号：TG317

出版年,卷(期):页码：2020,45(9):41-44

摘要：

ACP1000核电厂主泵泵壳锻件材料为ASME SA508-3低合金钢，该锻件形状复杂、质量大，锻造、热处理条件差，因此对冶炼、浇注、锻造、热处理以及检验等关键制造工艺提出了较高的要求。为了顺利获得质量可靠、性能优良的主泵泵壳锻件，从冶炼和浇注、锻造和热处理、机加工以及检验和试验4个方面，对主泵泵壳锻件制造的主要关键工艺及质量控制要点进行了介绍，并据此顺利制造出主泵泵壳锻件。经过各项检验、试验可知，该锻件无论在外观尺寸，还是在理化性能及无损检验指标方面，均满足ASME相关标准以及技术规格书的要求，且部分结果存在一定裕度，证明了该方法的可靠性和正确性，为主泵泵壳锻件的制造提供了一条可行道路。

The material of primary pump casing forgings for ACP1000 nuclear power plant is ASME SA508-3 low alloy steel, and the forgings have a complex shape, heavy weight and poor forging and heat treatment conditions. Therefore, higher requirements are put forward for key manufacturing processes such as smelting, casting, forging, heat treatment and inspection. In order to obtain the primary pump casing forgings with reliable quality and excellent performance, the main key processes and quality control points of the primary pump casing forgings were introduced from smelting and casting, forging and heat treatment, machining as well as inspection and test, and the primary pump casing forgings were successfully manufactured. After various inspections and tests, it is known that the forgings meet the requirements of ASME related standards and technical specifications in terms of appearance dimension, physical and chemical performances and nondestructive inspection indexes, and there is a certain margin for some results, which proves the reliability and correctness of this method, and provides a feasible way for the manufacturing of primary pump casing forgings.

基金项目：

张跃（1981-）,男，硕士，高级工程师 E-mail：nsczhangyue@163.com 通讯作者：李海涛（1979-），男，硕士，高级工程师 E-mail：seawave008@163.com

参考文献：

［1］广东核电培训中心. 900 MW压水堆核电站系统与设备
［M］. 北京: 原子能出版社，2005.

Guangdong Nuclear Power Training Center. 900 MW PWR Nuclear Power Plant System and Equipment
［M］. Beijing: Atomic Energy Press, 2005.

［2］邓冬, 赵立彬,张发云,等. AP1000核电厂主泵泵壳铸造及质量控制
［J］. 核科学与工程，2018，38(6): 1031-1034.

Deng D, Zhao L B, Zhang F Y, et al. Foundry and quality control of primary pump shell for AP1000 nuclear power plant
［J］. Nuclear Science and Engineering, 2018, 38(6):1031-1034.

［3］程剑，卢熙宁，赵正华. 基于2007版RCC-M规范的核主泵泵壳防快断分析
［J］. 通用机械，2019，(7):49-52.

Cheng J, Lu X N, Zhao Z H. Anti-quick break analysis of nuclear main pump shell based on 2007 RCC-M Code
［J］. General Machinery, 2019，(7): 49-52.

［4］ASME SA-508—2015, Specification for quenched and tempered vacuum-treated carbon and alloy steel forgings for pressure vessels
［S］.

［5］李昌义，刘正东，林肇杰. 核电站反应堆压力容器用钢的研究与应用
［J］.特殊钢，2010，31(4): 14-17.

Li C Y, Liu Z D, Lin Z J. Research and application of steels for reactor pressure vessel of nuclear power station
［J］. Special Steel, 2010, 31(4): 14-17.

［6］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.

［7］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.

［8］薛永栋，晋帅勇，汪勇，等. 核电压力容器用SA-508-3-1钢的冶炼
［J］. 大型铸锻件，2012，(6): 24-26.

Xue Y D, Jin S Y, Wang Y, et al. Smelting process of SA-508-3-1 steel for nuclear plant reactor pressure vessel
［J］. Heavy Casting and Forging, 2012, (6): 24-26.

［9］胡本芙，卜勇，吴承建，等. N/Al比值对A508-3钢的组织和性能的影响
［J］.钢铁，1999，(1): 39-43.

Hu B F, Bo Y, Wu C J, et al. Effect of N/Al ratio on microstructure and properties of A508-3 steel for nuclear reactor pressure vessel
［J］. Iron & Steel, 1999, (1): 39-43.

［10］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.

［11］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］. Harbin: Harbin Institute of Technology Press, 1999.

［12］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.

［13］陈红宇，刘正东，林肇杰，等. SA508-3钢平衡相转变的热力学计算和分析
［J］. 特殊钢，2007，28 (2): 19-21.

Chen H Y, Liu Z D, Lin Z J, et al. Thermodynamic calculation and analysis on equilibrium phases transformation in SA508-3 steel
［J］. Special Steel, 2007, 28(2): 19-21.

［14］ASTM E112—2013, Standard Test Methods for Determining Average Grain Size
［S］.

［15］ASTM E45—2018, Standard Test Methods for Determining the Inclusion Content of Steel
［S］.

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