[1] 郭鹏. 压水堆主冷却剂泵的发展 [J]. 装备机械, 2010(4): 43-48.

GUO P. Development of PWR reactor coolant pump [J]. The Magazine on Equipment Machinery, 2010(4): 43-48.
[2] 黄经国. 压水堆核电厂冷却剂主循环泵的技术历程和发展(Ⅰ) [J]. 水泵技术, 2009(4): 1-8.

HUANG J G. The technical process and development of the reactor coolant pump in PWR (Ⅰ) [J]. Pump Technology, 2009(4): 1-8.
[3] 黄经国. 压水堆核电厂冷却剂主循环泵的技术历程和发展(Ⅱ) [J]. 水泵技术, 2009(5): 1-7.

HUANG J G. The technical process and development of the reactor coolant pump in PWR [J]. Pump Technology, 2009(5): 1-7.
[4] 夏斌, 丁斐. 浅谈反应堆冷却剂泵 [J]. 产业与科技论坛, 2020, 19(21): 51-52. DOI:  10.3969/j.issn.1673-5641.2020.21.024.

XIA B, DING F. Brief talk about reactor coolant pump [J]. Estate and Science Tribune, 2020, 19(21): 51-52. DOI:  10.3969/j.issn.1673-5641.2020.21.024.
[5] 李中双, 符伟, 陈兴江, 等. 轴封型反应堆冷却剂泵结构的对比分析 [J]. 水泵技术, 2014(2): 26-28.

LI Z S, FU W, CHEN X J, et al. Comparative analysis of the structure of the shaft-dealed reactor coolant pump [J]. Pump Technology, 2014(2): 26-28.
[6] 王峰, 朱伟. 反应堆核主泵轴密封的设计特点 [J]. 城市建设理论研究(电子版), 2017(3): 138-139. DOI:  10.19569/j.cnki.cn119313/tu.201703091.

WANG F, ZHU W. Design features of shaft seal of reactor coolant pump [J]. Theoretical Research in Urban Construction, 2017(3): 138-139. DOI:  10.19569/j.cnki.cn119313/tu.201703091.
[7] 朱向东, 李天斌. 浅谈核主泵的国产化 [J]. 通用机械, 2014(7): 19-23. DOI:  10.3969/j.issn.1671-7139.2014.07.003.

ZHU X D, LI T B. Brief talk about the localization of RCP [J]. General Machinery, 2014(7): 19-23. DOI:  10.3969/j.issn.1671-7139.2014.07.003.
[8] 冯晓东, 吴大转, 杨立峰, 等. CNP1000轴封式核主泵技术 [J]. 排灌机械工程学报, 2016, 34(7): 553-560. DOI:  10.3969/j.issn.1674-8530.15.0162.

FENG X D, WU D Z, YANG L F, et al. Technology of CNP1000 shaft-sealed reactor coolant pump [J]. Journal of Drainage and Irrigation Machinery Engineering, 2016, 34(7): 553-560. DOI:  10.3969/j.issn.1674-8530.15.0162.
[9] 朱伟, 王峰, 王永革, 等. 压水堆核电站主泵的装配技术和管理 [J]. 核动力工程, 2019, 40(6): 144-148. DOI:  10.13832/j.jnpe.2019.06.0144.

ZHU W, WANG F, WANG Y G, et al. Technology and management of reactor coolant pumps assembling in pressurized water reactors [J]. Nuclear Power Engineering, 2019, 40(6): 144-148. DOI:  10.13832/j.jnpe.2019.06.0144.
[10] 韩惠东, 贾允, 张宇东. 轴封型核主泵全流量试验技术研究及试验分析 [J]. 大电机技术, 2017(2): 21-23. DOI:  10.3969/j.issn.1000-3983.2017.02.005.

HAN H D, JIA Y, ZHANG Y D. Technology research and test analyses of shaft sealing reactor coolant pump full load test [J]. Large Electric Machine and Hydraulic Turbine, 2017(2): 21-23. DOI:  10.3969/j.issn.1000-3983.2017.02.005.
[11]

ISE/31. Steel for quenching and tempering: DIN EN 10088-3 [S]. Brussels: European Committee for Standardization, 2006.
[12] 蔡龙. 核主泵推力轴承主瓦温差与装配关系研究 [J]. 电站系统工程, 2017, 33(4): 71-74.

CAI L. Research on relation of RCP thrust bearing pads temperature difference and assembly [J]. Power System Engineering, 2017, 33(4): 71-74.
[13] 鲁学良. 反应堆冷却剂泵推力滑动轴承试验台液压加载系统研究 [D]. 长沙: 湘潭大学, 2013.

LU X L. Development of the hydraulic loading system of a test rig for a reactor coolant pump thrust bearing [D]. Changsha: Xiangtan University, 2013.