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核电厂蒸汽发生器水化学参数的长期监督结果与评价
          
Long-term Monitoring Results and Evaluation of Water Chemistry Parameters Related to Steam Generator for a Nuclear Power Plant

摘    要
基于实际运行数据对某核电厂蒸汽发生器(SG)相关主要水化学参数的长期监督结果进行了趋势分析与评价。结果表明,机组自满功率商运以来SG二次侧水质运行状态总体良好,1/2号机组SG排污水系统杂质离子(Na+、SO42-、Cl-)运行燃料循环内平均浓度随运行堆年逐年降低并趋于稳定,分别达到0.5/0.4 μg/L、1.3/1.6 μg/L、0.9/0.8 μg/L;主给水系统总Fe运行燃料循环内平均浓度随运行堆年逐年降低并趋于稳定,达到0.9/0.7 μg/L;主给水系统溶解氧(DO)年均浓度均控制在期望值(3 μg/L)以下,但随运行堆年的增加呈现缓慢上升的趋势,泥渣沉积量上升与二次侧溶解氧含量升高呈现正相关性。对极限水化学条件可能引起的SG传热管腐蚀风险进行了评价,对有利于保持SG运行可靠性的水质运行工况控制及其优化提出了相关措施建议。
标    签 蒸汽发生器   水化学   评价   steam generator   water chemistry   evaluation  
 
Abstract
Based on the practical operating data, the trend analysis and evaluation of the long-term monitoring results of the main water chemistry parameters related to the steam generator (SG) for a nuclear power plant were carried out. The evaluation results show that since the units started to run at full power stage, the SG secondary side water quality was generally in good condition, and the annual average concentration of impurity ions (Na+, SO42-, Cl-) in the blow-down system of unit 1/2 decreased with operating reactor year and tended to stabilize, reaching 0.5/0.4 μg/L, 1.3/1.6 μg/L, and 0.9/0.8 μg/L respectively; the annual average concentration of Fe in the main water supply system decreased with operating reactor year and tended to stabilize, reaching 0.9/0.7 μg/L; the annual average concentration of dissolved oxygen (DO) in the main water supply system controlled below the expected value (3 μg/L), but with the increase in operating years, it showed a slow upward trend, and the increase in sludge deposition was positively correlated with the increase in dissolved oxygen content on the secondary side. The possible risk of corrosion of SG heat transfer tubes caused by very deviated water chemical conditions was evaluated. Relevant measures and suggestions were proposed for the control and optimization of water quality operating conditions that are conducive to maintaining the reliability of SG operation.

中图分类号 TG172   DOI 10.11973/fsyfh-202101014

 
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收稿日期 2020/6/28

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引用该论文: DAN Tichun,ZHAO Chuanli,GUI Chun. Long-term Monitoring Results and Evaluation of Water Chemistry Parameters Related to Steam Generator for a Nuclear Power Plant[J]. Corrosion & Protection, 2021, 42(1): 66


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参考文献
【1】田民顺,游兆金,刘祖洁. 秦山三核凝汽器泄漏对WANO化学性能指标的影响及其对策[J]. 中国核工业,2010(6):162-167.
 
【2】方岚. 秦山三期重水堆核电站二回路水化学优化[J]. 核科学与工程,2007,27(3):246-253.
 
【3】陶钧,孔德萍. 秦山核电厂二回路系统水化学的改进[J]. 中国工程科学,2008,10(1):91-96.
 
【4】LIU S,LU Y. Evaluation of SCC susceptibility of alloy 800 under candu SG secondary-side conditions[C]//Proceeding 5th CNS international steam generator conference November 26-29,2006. Toronto,Ontario,Canada:1-19.
 
【5】WANG J Q,LI X H,HUANG F,et al. Comparison of corrosion resistance of UNS N06690TT and UNS N08800SN in simulated primary water with various concentrations of dissolved oxygen[J]. Corrosion,2014,70(6):598-614.
 
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