METHOD OF MODELING STEAM GENERATOR AND PROCESSING STEAM GENERATOR TUBE DATA OF NUCLEAR POWER PLANT

• 1. 核电厂蒸汽发生器U形传热管用支撑板及其蒸汽发生器 [P] . 中国专利： CN208398051U . 2019.01.18
• 2. 操作蒸汽发生器的方法、蒸汽发生器和具有蒸汽发生器的烹饪装置 [P] . 中国专利： CN112971516A . 2021-06-18
• 3. METHOD OF MODELING STEAM GENERATOR AND PROCESSING STEAM GENERATOR TUBE DATA OF NUCLEAR POWER PLANT [P] . CA2777939C . 2018-02-06

  机译： 核电厂蒸汽发生器建模和蒸汽发生器管数据处理方法

• 4. METHOD OF MODELING STEAM GENERATOR AND PROCESSING STEAM GENERATOR TUBE DATA OF NUCLEAR POWER PLANT [P] . 韩国专利： KR101665157B1 . 2016-10-11

  机译： 核电厂蒸汽发生器建模和蒸汽发生器管数据处理方法

• 5. METHOD OF MODELING STEAM GENERATOR AND PROCESSING STEAM GENERATOR TUBE DATA OF NUCLEAR POWER PLANT [P] . 欧洲知识产权局专利： EP2499452A4 . 2016-01-27

  机译： 核电厂蒸汽发生器建模和蒸汽发生器管数据处理方法

• 1. Transient Analysis of Steam Generator in PWR Nuclear Power Plant [J] . 上海大学学报（英文版） . 1998,第002期
• 2. 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
• 3. Signal processing schemes for Eddy Current Testing of steam generator tubes of nuclear power plants [J] . Shuxia Tian, Zhenmao Chen, Masashi Ueda, Nuclear Engineering and Design . 2012,第Apra期
• 4. Effects of curative and preventive chemical cleaning processes on fouled steam generator tubes in nuclear power plants [J] . Goujon C., Pauporte Th., Bescond A., Nuclear Engineering and Design . 2017,第nova期
• 5. New method to assess tube support plate clogging phenomena in steam generators of nuclear power plants [J] . D. Bouskela, V. Chip, B. El Hefni, Mathematical and Computer Modelling of Dynamical Systems . 2010,第3期
• 6. DAMAGE MODELING OF THE LOAD-BEARING CAPACITY OF DAMAGED STEAM GENERATOR TUBES IN NUCLEAR POWER PLANTS [C] . Xaver Schuler, Sarah Gehrlicher, Michael Seidenfuss, ASME Pressure Vessels and Piping conference . 2014
• 7. NUCLEAR POWER PLANT MODELING AND STEAM GENERATOR STABILITY ANALYSIS [D] . KORNFILT, JAK 1981
• 8. Low Cycle Fatigue Behavior of Steam Generator Tubes under Axial Loading [O] . Xing He, Junfeng Chen, Wei Tian, 2018
• 9. Growth Model of Circumferential Outer Diameter Stress Corrosion Crack in Retired Steam Generator Tube of Kori 1 Nuclear Power Plant [O] . Dong-jin Kim, Hong Pyo Kim, Joung Soo Kim, 2015

• 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. Performance and Economic Study of Oxy-fuel Gas Turbine Power Plant Utilizing Nuclear Steam Generator [J] . K. Oshima ,Y. Uchiyama . 能源与动力工程 . 2010,第008期
• 3. Fault Diagnosing System of Steam Generator for Nuclear Power Plant Based on Fuzzy Neural Networks [J] . Ming-Yu Fu ,Xin-Qian Bian ,Ji Shi . 船舶与海洋工程学报：英文版 . 2002,第1期
• 4. 福清核电厂蒸汽发生器排污除盐床氨化运行研究 [C] . CHEN Yong ,陈勇 ,CHENG Xiu . 中国核学会2022年学术年会 . 2017
• 5. 直流蒸汽发生器模块精细化建模与仿真 [A] . 童秋实 . 2020