Steam power plant for nuclear energy - power stations, in particular with pressurized water - or boiling water reactors

• 1. 具有后热排除管路的热核反应堆系统及该管路对沸水和压水核反应堆的应用 [P] . 中国专利： CN1041665A . 1990-04-25
• 2. 沸水反应堆的反应堆压力壳以及用于该沸水反应堆的反应堆压力壳中的汽水分离的方法 [P] . 中国专利： CN100495583C . 2009.06.03
• 3. steam system for nuclear power plants, in particular with pressurized water or boiling water reactors [P] . 德国专利： DE000001107244A . 1961-05-25

  机译： 核电站的蒸汽系统，尤其是带有压水或沸水反应堆的蒸汽系统

• 4. STEAM POWER PLANT FOR NUCLEAR POWER STATIONS HAVING PRESSURIZED WATER REACTORS [P] . CA992000A . 1976-06-29

  机译： 带有加压水反应器的核电站蒸汽电厂

• 5. Steam power plant for nuclear power stations - with pressurized water reactors [P] . 德国专利： DE2136185A1 . 1973-02-01

  机译： 核电站蒸汽电厂-带有压水堆

• 1. Development and Application of Maintenance Template in Pressurized Water Reactor Nuclear Power Plant [J] . ZHANG Sheng, CHEN Yu, CAO Zhi-peng, 东华大学学报（英文版） . 2015,第001期
• 2. Assessment of Effects of Qinshan Nuclear Power Station on the Ecological Environment and Water Quality of its Adjacent Waters after its Running [J] . 海洋通报：英文版 . 1999,第002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. A Novel Computerized Water Level Control System of PWR Steam Generator of Nuclear Power Plant [J] . 先进制造进展：英文版 . 1998,第003期
• 5. Phytoplankton ecology in the adjacent waters of the Daya Bay Nuclear Power Station in Guangdong in spring [J] . 海洋学报：英文版 . 1992,第004期
• 6. SEISMIC TEST RESULTS OF THE MAIN STEAM ISOLATION VALVE FOR JAPANESE BOILING WATER REACTOR NUCLEAR POWER PLANTS [C] . Hideaki Itabashi, Yoshitaka Tsutsumi, Koji Nishino, ASME Pressure Vessels and Piping Conference . 2020
• 7. MODELING AND SIMULATION OF PRESSURIZED WATER REACTOR POWER PLANT. [D] . WANG, SHIH-JEN. 1983
• 8. Monitoring of Tritium Internal Exposure Doses of Heavy-Water Reactor Workers in Third Qinshan Nuclear Power Plant [O] . Kong-Zhao Wang, Lei Sun, Kou-Hong Xiong, 2019
• 9. Experiments and Analytical Simulation on Steam-Injector-Driven Passive Core Injection System for Innovative-Simplified Nuclear Power Plant(Light Water Reactor・Advanced Reactor,Power and Energy System Symposium) [O] . Shuichi OHMORI, Tadashi NARABAYASHI, Michitsugu MORI, 2009
• 10. Layout of the Safety Analysis Report for Nuclear Power Plants with Pressurized Water Reactor or Boiling Water Reactor in the Federal Republic of Germany [R] . Albrecht, E. 1980

• 1. 基于时域方法的核电站沸水反应堆试验模态参数识别 [C] . 张明星 ,柳亦兵 ,辛卫东 . 第29届中国控制会议 . 2010
• 2. 核电站沸水反应堆结构试验模态分析 [A] . 张明星 . 2011