水化学工况对四代核电直流蒸汽发生器用<strong>T22</strong>钢应力腐蚀开裂行为的影响

doi:10.11902/1005.4537.2025.298

中国腐蚀与防护学报

2026, Vol. 46

Issue (4): 1067-1080 CSTR: 32134.14.1005.4537.2025.298 DOI: 10.11902/1005.4537.2025.298

研究报告

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水化学工况对四代核电直流蒸汽发生器用T22钢应力腐蚀开裂行为的影响

王磊¹, 陶泽宇², 刘锋³, 匡文军⁴(

), 马鑫², 姚尧³, 张国威¹

^1.中核霞浦核电有限公司宁德 355100
^2.西安交通大学材料科学与工程学院西安 710049
^3.西安热工研究院有限公司西安 710054
^4.华南理工大学材料科学与工程学院广州 510641

Effect of Water Chemistry on Stress Corrosion Cracking of T22 Steel Used in Once Through Steam Generator of Nuclear Power

WANG Lei¹, TAO Zeyu², LIU Feng³, KUANG Wenjun⁴(

), MA Xin², YAO Yao³, ZHANG Guowei¹

^1.CNNC Xiapu Nuclear Power Co. Ltd., Ningde 355100, China
^2.School of Materials Science and Engineering, Xi'an Jiaotong University, Xi'an 710049, China
^3.China Xi'an Thermal Power Research Institute Co. Ltd., Xi'an 710054, China
^4.School of Materials Science and Engineering, South China University of Technology, Guangzhou 510641, China

引用本文:

王磊, 陶泽宇, 刘锋, 匡文军, 马鑫, 姚尧, 张国威. 水化学工况对四代核电直流蒸汽发生器用T22钢应力腐蚀开裂行为的影响[J]. 中国腐蚀与防护学报, 2026, 46(4): 1067-1080.
Lei WANG, Zeyu TAO, Feng LIU, Wenjun KUANG, Xin MA, Yao YAO, Guowei ZHANG. Effect of Water Chemistry on Stress Corrosion Cracking of T22 Steel Used in Once Through Steam Generator of Nuclear Power[J]. Journal of Chinese Society for Corrosion and protection, 2026, 46(4): 1067-1080.

全文: PDF(42532 KB) HTML

摘要:

高温气冷堆(HTGRs)及钠冷快堆(SFRs)等四代核电机组直流蒸发器的给水处理方式均为还原性全挥发处理[AVT(R)]，该处理方式容易引发构件的流动加速腐蚀，导致传热管节流阀堵塞等问题。水化学加氧处理是解决节流阀堵塞问题的有效方式，然而水介质溶解氧含量的提高是否影响构件的应力腐蚀开裂(SCC)敏感性，需要进一步验证。本文以四代核电直流蒸发器蒸发段使用的T22钢为研究对象，通过慢应变速率拉伸实验(SSRT)，评估了其在还原性全挥发处理工况、氧化性全挥发处理[AVT(O)]工况和加氧处理(OT)工况下的SCC行为。结果表明，水环境中溶解氧浓度的增加不会显著改变T22钢的氧化行为。氧化性全挥发处理或加氧处理，不会提升T22钢的应力腐蚀敏感性。本文为解决节流阀沉积问题提供了技术依据，为四代核电蒸汽发生器给水水化学参数的调整提供了参考。

关键词 ：钠冷快堆, 给水加氧, 应力腐蚀开裂, 慢应变速率拉伸实验, T22 钢

Abstract：

For the known generation IV nuclear power plants, such as high-temperature gas-cooled reactors (HTGRs) and sodium-cooled fast reactors (SFRs), once-through steam generators typically adopt a reducing all-volatile treatment [AVT(R)] as the feedwater chemistry control strategy. However, this water chemistry induces flow-accelerated corrosion (FAC) for the related structural components, which can result in heat-transfer tube fouling and throttling valve blockage. Oxygenated treatment (OT) is an effective approach to mitigate throttling valve deposition. Nevertheless, the potential impact of increased dissolved oxygen on the stress corrosion cracking (SCC) susceptibility of structural materials remains to be clarified. In this study, the SCC behavior of T22 steel, widely used in the evaporator section of once-through steam generators in Generation IV reactors, was systematically evaluated in conditions of AVT(R), AVT(O), and OT respectively by using slow strain rate tensile (SSRT) tests. The results demonstrate that an increased dissolved oxygen concentration does not significantly alter the oxidation behavior of T22 steel. Importantly, the adoption of oxidizing AVT or OT conditions does not increase the SCC susceptibility of T22 steel. This work provides a technical foundation for addressing throttling valve deposition in once-through steam generators and offers valuable guidance for optimizing feedwater chemistry in generation IV nuclear power systems.

Key words： sodium-cooled fast reactor feed water oxygenation stress corrosion cracking slow strain rate tensile test T22 steel

收稿日期: 2025-09-16 32134.14.1005.4537.2025.298

ZTFLH:

TG174

通讯作者: 匡文军，E-mail：wjkuang@scut.edu.cn，研究方向为核材料环境损伤

Corresponding author: KUANG Wenjun, E-mail: wjkuang@scut.edu.cn

作者简介: 王磊，男，1981年生，硕士，高级工程师陶泽宇，男，2001年生，硕士生
陶泽宇，男，2001 年生，硕士生

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表1 实验用T22钢的化学成分

图1 T22钢原始组织形貌及室温力学性能测试结果

表2 换热管T22钢材质安全性评价实验条件

图2 刻痕测量及拉伸试样尺寸示意图

图3 应变速率为5 × 10-8 /s的SSRT曲线

图4 6种工况条件下T22钢SSRT后的表面形貌SE形貌

图5 6种工况条件下T22钢SSRT后试样截面BSE形貌

图6 应变速率为5 × 10-7 /s下试样在低温和高温下SSRT曲线

图7 AVT(R)-低温工况下T22钢拉断试样表面形貌

图8 AVT(R)-高温工况下T22钢拉断试样表面形貌

图9 OT-低温工况下T22钢拉断试样表面形貌

图10 OT-高温工况下T22钢拉断试样表面形貌

图11 AVT(R)-低温工况下T22钢拉断试样断口形貌

图12 AVT(R)-高温工况下T22钢拉断试样断口形貌

图13 OT-低温工况下T22钢拉断试样断口形貌

图14 OT-高温工况下T22钢拉断试样断口形貌

图15 不同温度OT工况下T22钢试样断口断裂类型统计

图16 6种工况条件下T22钢静态浸泡试样截面形貌

图17 T22钢在低温和高温浸泡实验后表面氧化物XRD谱

表3 两种工况条件下T22钢试样拉伸实验结果对比

图18 在15 MPa高温高压水中Fe-Cr二元体系中Fe组分的Pourbaix图(Fe[aq]tot = Cr[aq]tot = 10-6 mol)

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