Investigation of Thermohydraulic Processes in Steam Generators for Nuclear Power Stations Equipped with VVER Reactors

N. B. Trunov

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Investigation of Thermohydraulic Processes in Steam Generators for Nuclear Power Stations Equipped with VVER Reactors

机译：装有VVER反应堆的核电站蒸汽发生器中热工水力过程的研究

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The results obtained from experimental investigations and mathematical simulation of horizontal steam generators are considered. Recommendations for continuing these works are given.

机译：考虑从水平蒸汽发生器的实验研究和数学模拟获得的结果。给出了继续进行这些工作的建议。

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《Thermal engineering》 |2006年第1期|p.26-36|共11页
作者
N. B. Trunov;
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作者单位

Gidropress Experimental Design Office (OKB Gidropress), ul. Ordzhonikidze 21, Podol'sk, Moscow oblast, 142103 Russia;

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正文语种 eng
中图分类发电、发电厂;
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1. Specific Features of Corrosion Damage to Heat-Transfer Tubes of Steam Generators Used at Nuclear Power Stations Equipped with VVER-1000 Reactors [J] . D. S. Nemytov, V. F. Tyapkov Thermal engineering . 2009,第7期

机译：配备VVER-1000反应堆的核电站所用蒸汽发生器的传热管的腐蚀损坏的特殊特征
2. The Capacities of a Corrosion-Fatigue Monitoring System in Managing the Service Life of Steam Generators Operating at Nuclear Power Stations Equipped with a VVER-1000M Reactor [J] . G. F. Banyuk, O. P. Arkhipov, S. I. Brykov, Thermal engineering . 2007,第2期

机译：腐蚀疲劳监测系统在管理配备VVER-1000M反应堆的核电站中运行的蒸汽发生器的使用寿命方面的能力
3. Consideration of Field Experience in Developing New Projects of Steam Generators for Nuclear Power Stations Equipped with VVER Reactors [J] . N. B. Trunov, V. V. Denisov, S. A. Kharchenko, Thermal engineering . 2006,第1期

机译：对开发配备VVER反应堆的核电站蒸汽发生器新项目的现场经验的思考
4. A Moessbauer Study of Austenitic Steel Originating from the Steam Generator of a VVER-440 Type Nuclear Reactor, Paks, Hungary [C] . Z. HOMONNAY, E. KUZMANN, K. VARGA, International symposium on the industrial applications of the mossbauer effect . 2002

机译：来自Vver-440型核反应堆的蒸汽发生器的奥氏体钢的Moessbauer研究，匈牙利
5. NUCLEAR POWER PLANT MODELING AND STEAM GENERATOR STABILITY ANALYSIS [D] . KORNFILT, JAK 1981

机译：核电站建模与蒸汽发生器稳定性分析
6. A novel inspection robot for nuclear station steam generator secondary side with self-localization [O] . Jinke Li, Xinyu Wu, Tiantian Xu, -1

机译：具有自定位功能的新型核电站蒸汽发生器二次侧检查机器人
7. Experimental investigation of heat and mass exchange processes during operation of VVER steam generator in emergency condensing mode [O] . A.S. Shlyopkin, A.V. Morozov, D.S. Kalyakin, 2017

机译：VVER蒸汽发生器应急冷凝运行过程中换热过程的实验研究
8. Standards for Calculating Strength of Reactor Components,Steam Generators,Vessels,and Piping of Atomic Power Stations,Test and Research Reactors,and Installations. [R] . 1976

机译：计算原子发电站，测试和研究反应堆以及装置的反应堆组件，蒸汽发生器，容器和管道强度的标准。

Investigation of Thermohydraulic Processes in Steam Generators for Nuclear Power Stations Equipped with VVER Reactors

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