dampferzeugungsanlage with a tube formed from a steam generator at one end of the rohrsystems water down and at the other end of steam can be taken from

• 1. 在管子里特别是在核电站的蒸汽发生器的管子里遥控焊接衬管的设备 [P] . 中国专利： CN1028620C . 1995.05.31
• 2. 在管子里特别是在核电站的蒸汽发生器的管子里遥控焊接衬管的方法和设备 [P] . 中国专利： CN1043103A . 1990-06-20
• 3. dampferzeugungsanlage with a hochdruckdampferzeuger,when the equipment as speiseflüssigkeit one end of at least one rohrsystems fed and at the other end as the overheated steam is removed. [P] . 瑞士专利： CH174175A . 1934-12-31

  机译： 当设备作为至少一个回转系统的一端进料，而另一端则是去除过热的蒸汽时，请用汽缸将其浸湿。

• 4. A tube for a steam generator having a rib therein, a steam generator using the tube, and a steam generator for a steam generator, [P] . 韩国专利： KR960705176A . 1996-10-09

  机译： 用于具有肋的蒸汽发生器的管，使用该管的蒸汽发生器以及用于蒸汽发生器的蒸汽发生器，

• 5. STEAM GENERATOR TUBE CLEANER AND STEAM GENERATOR TUBE CLEANNING METHOD FOR PRESSUIZED HEAVY WATER REACTOR [P] . 韩国专利： KR20150060371A . 2015-06-03

  机译： 加压重水反应器的汽轮发电机管道清洗器及汽轮发电机管道清洗方法

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• 2. Modeling a high output marine steam generator feedwater control system which uses parallel turbine-driven feed pumps [J] . QIU Zhi-qiang, ZOU Hai, SUN Jian-hua 船舶与海洋工程学报（英文版） . 2008,第003期
• 3. A Novel Computerized Water Level Control System of PWR Steam Generator of Nuclear Power Plant [J] . 上海大学学报（英文版） . 1998,第003期
• 4. The Effect of Polyacrylic Acid on Iron Oxides Formed on Steam Generator Tubes and on Metallic Copper Present in Pressurized Water Reactors [C] . Marion Roy, Carine Mansour, Dominique You Nuclear Plant Chemistry Conference . 2015
• 5. Transient Analysis of the NuScale Power Helical-Coil Steam Generator Tube Rupture Using RELAP5-3D [D] . Johnson, Kyle P. 2021
• 6. Optical Fiber Demodulation System with High Performance for Assessing Fretting Damage of Steam Generator Tubes [O] . Peijian Huang, Ning Wang, Junying Li, 2018
• 7. ROLE OF BOILING MODE AND RATE IN FORMATION OF WATERSIDE DEPOSITS IN HEAT RECOVERY STEAM GENERATOR EVAPORATOR TUBES [O] . David S Moelling, James Malloy 2015
• 8. Steam Generator Tube Performance. Experience with Water-Cooled Nuclear Power Reactors During 1982 [R] . Tatone, O. S., Pathania, R. S. 1984

• 1. Analysis of the Break Size Influence on the Damage Accident of Single Heat Transfer Tube of Ship Nuclear Power Steam Generator [J] . Meng Cai ,Wei Wang ,Junzhong Sun . 世界工程和技术（英文） . 2017,第4期
• 2. Verification of Integrity of Steam Generator Tubes by Pressure Testing [J] . Yong-Seok Kang ,Min-Woo Nam ,Jai-Hak Park . 能源与动力工程 . 2013,第012期
• 3. 对压水堆核电厂蒸汽发生器传热管子破裂事故诊断及处置的研究 [C] . 黄芳芝 . 中国核学会核能动力学会第五届年会 . 1994
• 4. 核电蒸汽发生器管子管板液压胀接技术研究 [A] . 陆军 . 2015