压水堆(pressurized water reactor, PWR) 核电站一次侧运行水化学的优化控制是减少辐射剂量, 防止关键设备腐蚀损伤, 保持燃料性能的最经济、最有效的途径之一, 其本质是通过水化学与设备材料的交互作用改善材料表面氧化膜的特性. 综述了PWR 核电站一次侧主冷却剂水化学与设备材料腐蚀损伤关系的研究现状及问题, 介绍了近年来在PWR 一次侧注Zn 水化学(Zn-injected water chemistry, ZWC) 方面的应用基础研究进展.
吴欣强1,2,3, 刘侠和1,2,3, 韩恩厚1,2,3, 柯伟1,2,3
. 压水堆核电站一次侧水化学与设备材料腐蚀损伤的关系[J]. 上海大学学报(自然科学版), 2015
, 21(2)
: 141
-151
.
DOI: 10.3969/j.issn.1007-2861.2014.04.015
Optimization of primary water chemistry is one of the most effective ways to minimize radiation field, mitigate material degradation and maintain fuel performance in pressurized water reactor (PWR) nuclear power plants. It improves characteristics of oxide scales formed on the materials of equipment due to interactions between water chemistry and materials. This article reviews the current status and related problems of the relationship between water chemistry of primary coolant and material degradation in PWR nuclear power plants. Fundamental research progress achieved in recent years on Zn-injected water
chemistry (ZWC) into primary coolants of PWR is introduced.
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