Effect of the Quality of the Coolant on the Operating Reliability of Items of Equipment at Nuclear Power Stations with RBMK-1000 Reactors

V.G. Kritsii; P.S. Styazhin; I.G. Berezina

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Effect of the Quality of the Coolant on the Operating Reliability of Items of Equipment at Nuclear Power Stations with RBMK-1000 Reactors

机译：冷却液质量对带有RBMK-1000反应堆的核电站设备项目运行可靠性的影响

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Experience in qualitatively appraising the effect that the quality of the coolant has on the reliability of items of the equipment at nuclear power stations with RBMK-1000 reactors is presented. A correlation between the quality indices of the coolant and the reliability of the mot important items of equipment in the multiple forced circulation circuit (MFCC), including the fuel-rod assemblies, is established. The quality of the coolant depends on the operating reliability of the condenser installation, the sensitivity and adequacy of the pickups of automated chemical control (ACC), and the efficiency of condense polishing. Using correction technologies improves the operating reliability of the items of the equipment.

机译：介绍了定性评估冷却剂质量对带有RBMK-1000反应堆的核电站设备项目可靠性的影响的经验。建立了包括燃料棒组件在内的多强制循环回路（MFCC）中冷却剂的质量指标与设备的重要部件的可靠性之间的关系。冷却剂的质量取决于冷凝器设备的运行可靠性，自动化学控制（ACC）传感器的灵敏度和充分性，以及冷凝抛光的效率。使用校正技术可提高设备各项目的操作可靠性。

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《Thermal engineering》 |2000年第7期|569-578|共10页
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V.G. Kritsii; P.S. Styazhin; I.G. Berezina;
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1. Formation of Corrosion Products in the Coolant and Deposits in the Multiple Forced Circulation Circuit of a Nuclear Power Station Equipped with an RBMK-1000 Reactor [J] . V. F. Tyapkov, L. P. Khamyanov, I. Yu. Chudakova, Thermal engineering . 2007,第12期

机译：配备RBMK-1000反应堆的核电站多强迫循环回路中冷却剂中腐蚀产物的形成和沉积物
2. The Introduction of Precoat Ion-Exchange Filtration in Special Water-Treatment Plants at Operating RBMK-1000 Reactor-Based Nuclear Power Stations [J] . V. F. Tyapkov, I. Yu. Chudakova, V. M. Tishkov, Thermal engineering . 2005,第7期

机译：在基于RBMK-1000反应堆的核电站运行的特殊水处理厂中引入预涂层离子交换过滤
3. The Thermal Process Diagram and Equipment of the Secondary Coolant Circuit of a Nuclear Power Station Unit Based on the BREST-OD-300 Reactor Installation for Subcritical Steam Conditions [J] . Yu. V. Nesterov, A. S. Lisyanskii, E. I. Makarova, Thermal engineering . 2011,第6期

机译：基于BREST-OD-300反应堆的亚临界蒸汽条件下核电站机组二次冷却回路的热过程图和设备
4. Improving reactor coolant pump seal reliability at Dominion Surry nuclear power station [C] . G. van Loenhout, A. J. Olson, J. R. Olliver International Conference on Fluid Sealing . 2011

机译：挖掘统治核电站改善反应堆冷却剂泵密封可靠性
5. Probabilistic risk assessment for a loss of coolant accident in McMaster Nuclear Reactor and application of reliability physics model for modeling human reliability. [D] . Ha, Taesung. 2007

机译：McMaster核反应堆中冷却剂损失事故的概率风险评估，以及用于建立人类可靠性模型的可靠性物理模型的应用。
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: Pereguda AI (2019) Reliability of the RBMK-1000 coolant flow measurement system. Nuclear Energy and Technology 5(1): 81-87. https://doi.org/10.3897/nucet.5.34296 [O] . Arkady I. Pereguda 2019

机译：图3来自：Pereguda AI（2019）RBMK-1000冷却剂流量测量系统的可靠性。核能和技术5（1）：81-87。 https://doi.org/10.3897/nucet.5.34296
8. Transition to an Operating Reactor Environment - Implications for NRC (Nuclear Regulatory Commission) Quality Assurance Programs Based on Nuclear Power Industry and Regulatory Projections through 1995. [R] . Christensen, J. A., Schuller, C. R., Harty, H., 1986

机译：过渡到运行的反应堆环境 - 对NRC（核管理委员会）基于核电行业和监管预测的质量保证计划的影响到1995年。

Effect of the Quality of the Coolant on the Operating Reliability of Items of Equipment at Nuclear Power Stations with RBMK-1000 Reactors

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