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STUDY AND DESIGN OF MONITORING SYSTEM OF REACTOR COOLANT PUMP IN NUCLEAR POWER PLANT

机译：核电厂反应堆冷却泵监控系统的研究与设计

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You Lei; Sun Fuchun; Chengdu Sichuan; He Pan; Xu Hongkun;
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1. The development of reactor coolant pump vibration monitoring and a diagnostic system in the nuclear power plant [J] . In Soo Koo, Whan Woo Kim ISA Transactions . 2000,第3期

机译：核电站反应堆冷却剂泵振动监测和诊断系统的开发
2. Structural Integrity Evaluation for Interference-fit Flywheels in Reactor Coolant Pumps of Nuclear Power Plants [J] . June-soo Park, Ha-cheol Song, Ki-seok Yoon, Journal of Mechanical Science and Technology . 2005,第11期

机译：核电站反应堆冷却剂泵中过盈配合飞轮的结构完整性评估
3. Structural Integrity Evaluation for Interference-fit Flywheels in Reactor Coolant Pumps of Nuclear Power Plants [J] . June-soo Park, Ha-cheol Song, Ki-seok Yoon, Journal of Mechanical Science and Technology . 2005,第11期

机译：核电站反应堆冷却剂泵中过盈配合飞轮的结构完整性评估
4. STUDY AND DESIGN OF MONITORING SYSTEM OF REACTOR COOLANT PUMP IN NUCLEAR POWER PLANT [C] . You Lei, Sun Fuchun, He Pan, ICONE18;International conference on nuclear engineering . 2011

机译：核电厂反应堆冷却泵监控系统的研究与设计
5. Design of a shield system for a hyper-pure germanium detector as a stack monitor for use in accident conditions at a nuclear power plant [D] . Petito, Anthony Bruno 1993

机译：超高纯锗探测器的屏蔽系统的设计，该系统用作核电站事故条件下的烟囱监测器
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. Figure 3 from: Beznosov AV, Bokov PA, Lvov AV, Bokova TA, Volkov NS, Marov AR (2020) Experimental studies into the performance of the lead coolant axial pump wet ends to justify main circulation pumps for the HMLC reactor plant circuits. Nuclear Energy and Technology 6(3): 143-147. https://doi.org/10.3897/nucet.6.57736 [O] . Aleksandr V. Beznosov, Pavel A. Bokov, Aleksandr V. Lvov, 2020

机译：图3来自：Beznosov AV，Bokov Pa，LVov AV，Bokova TA，Volkov NS，Marov AR（2020）对铅冷却液轴向泵湿端的性能进行实验研究，以证明HMLC反应器厂电路的主循环泵。核能和技术6（3）：143-147。 https://doi.org/10.3897/nucet.6.57736
8. Reactor Safety Study:An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix VII. Release of Radioactivity in Reactor Accidents. Appendix VIII. Physical Processes in Reactor Meltdown Accidents. Appendix IX. Safety Design Rationale for Nuclear Power Plants. Appendix X. Design Adequacy. [R] . 1976

机译：反应堆安全研究：美国商业核电厂事故风险评估。附录七。反应堆事故中放射性的释放。附录八。反应堆熔毁事故中的物理过程。附录九。核电厂安全设计理念。附录X.设计充分性。

STUDY AND DESIGN OF MONITORING SYSTEM OF REACTOR COOLANT PUMP IN NUCLEAR POWER PLANT

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