核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展

doi:10.11902/1005.4537.2020.101

中国腐蚀与防护学报

2021, Vol. 41

Issue (4): 417-428 DOI: 10.11902/1005.4537.2020.101

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核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展

焦洋, 张胜寒(

), 檀玉

华北电力大学 (保定) 环境科学与工程系保定 071003

Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water

JIAO Yang, ZHANG Shenghan(

), TAN Yu

Department of Environment Science and Engineering, North China Electric Power University, Baoding 071003, China

全文: PDF(2782 KB) HTML

摘要:

综述了作为核电结构材料的不锈钢在高温高压水环境中的应力腐蚀开裂 (SCC) 行为，讨论了材料性能、加载方式、水化学环境等因素对应力腐蚀敏感性、裂纹萌生与扩展速率的影响，介绍了较成熟锌注入技术的发展历程及其对压水堆一次侧应力腐蚀 (PWSCC) 的影响作用。最后综合考虑各方面因素和实际运行情况，总结了降低SCC敏感性的方法，并提出未来研究中应重点关注的问题。

关键词 ：核电站, 不锈钢, 应力腐蚀开裂, 锌注入技术

Abstract：

Stress corrosion cracking behavior (SCC) of typical nuclear structural materials stainless steel in high-temperature and high-pressure water was reviewed. The effect of material type, mechanical properties, water chemistry on the sensitivity, initiation and propagation of cracks were discussed. The development of the zinc injection technology in the coolant system and its inhibitory effect on the primary side stress corrosion (PWSCC) were introduced. Finally, by taking various factors and actual operating conditions into consideration, the method of reducing the sensitivity of SCC was summarized, and the problems that should be focused on in future research were proposed.

Key words： nuclear power plant stainless steel SCC zing injection technology

收稿日期: 2020-06-12

ZTFLH:

TG174

通讯作者: 张胜寒 E-mail: shenghan_zhang@126.com

Corresponding author: ZHANG Shenghan E-mail: shenghan_zhang@126.com

作者简介: 焦洋，女，1994年生，博士生

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焦洋, 张胜寒, 檀玉. 核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展[J]. 中国腐蚀与防护学报, 2021, 41(4): 417-428.
Yang JIAO, Shenghan ZHANG, Yu TAN. Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water. Journal of Chinese Society for Corrosion and protection, 2021, 41(4): 417-428.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2020.101 或 https://www.jcscp.org/CN/Y2021/V41/I4/417

图1 屈服强度对不锈钢SCC扩展速率的影响[15,29]

图2 在高温含氧水中不锈钢的裂纹扩展速率随应力强度因子的变化[32,33]

图3 温度、热处理、表面状态对304不锈钢应力腐蚀开裂的影响[44]

图4 pH对304L、316L、法国Z6CND17.12奥氏体不锈钢SCC的影响[47-49]

Parameter	AP1000	Qinshan nuclear power Plant
Conductivity	1~40 μS/cm (25 ℃)	1~40 μS/cm (25 ℃)
pH	4.2~10.5 (25 ℃)	5.4~10.5 (25 ℃)
O₂	$≤$ 0.1 mg/L	$≤$ 0.1 mg/L
Cl^-	$≤$ 0.15 mg/L	$≤$ 0.1 mg/L
F^-	$≤$ 0.15 mg/L	---
H₂	25~50 cm³ (STP)/kg H₂O	25~35 cm³ (STP)/kg H₂O
Suspended solids	$≤$ 0.2 mg/L	$≤$ 1.0 mg/L
LiOH	---	0.22~2.2 mg/L
H₃BO₃	0~4000 mg/L (calculated as B)	0~2400 mg/L (calculated as B)

表1 压水堆机组一回路冷却剂系统水质要求

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