硅酸盐学报

核电厂硼酸腐蚀混凝土微观结构和宏观性能的退化

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荣华 ¹ , 耿岩 ¹ , 陶钧 ² , 周欣竹 ³ , 郑建军 ³

硅酸盐学报 | 混凝土耐久性机理表征与预测方法专题—研究论文 2026,54(2): 754-767

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硅酸盐学报 |混凝土耐久性机理表征与预测方法专题—研究论文 2026 , 54 (2) : 754 -767

核电厂硼酸腐蚀混凝土微观结构和宏观性能的退化

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荣华¹, 耿岩¹, 陶钧², 周欣竹³, 郑建军³

作者信息

^1．中冶建筑研究总院有限公司，北京 100088

^2．中国核工业集团公司运维技术有限公司，杭州 311215

^3．浙江工业大学土木工程学院，杭州 310023

通讯作者:

耿岩（1988—），女，博士，高级工程师。

作者简介:

荣华（1985—），女，博士，正高级工程师。

Degradation of Microstructure and Macroscopic Performance of Boric Acid-Corroded Concrete in Nuclear Power Plants

Hua RONG¹, Yan GENG¹, Jun TAO², Xinzhu ZHOU³, Jianjun ZHENG³

Affiliations

^1.Metallurgical Group Corporation of China, Beijing 100088, China

^2.Operation and Maintenance Technology Co., Ltd., China National Nuclear Corporation, Hangzhou 311215, China

^3.College of Civil Engineering, Zhejiang University of Technology, Hangzhou 310023, China

Corresponding Author:

GENG Yan (1988-), female, Ph.D., Senior Engineer. E-mail: gengyan11@163.com

RONG Hua (1985-), female, Ph.D., Professor of Engineering. E-mail: ronghua@cribc.com

出版时间: 2026-02-20 doi: 10.14062/j.issn.0454-5648.20250550

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摘要

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在核电厂运行过程中，硼酸溶液因意外发生泄漏并腐蚀混凝土结构，导致其宏观力学性能退化，深入研究该退化机理与规律对于准确评估核电站结构长期安全性与服役寿命具有至关重要的工程现实意义。采用试验测试与理论分析相结合的方法，系统研究了硼酸腐蚀环境下混凝土微观结构与宏观性能的退化。通过开展超声波速、质量损失率、轴心抗压强度损失率和劈裂抗拉强度损失率试验，获取了混凝土在硼酸环境下的性能演化数据。基于试验结果，定量分析了浸泡时间、硼酸浓度、温度和水胶比对混凝土性能退化的影响，并深入探讨了硼酸浓度、温度和水胶比之间的耦合效应。研究结果表明：随着硼酸浓度增加、温度升高以及水胶比增大，混凝土微观结构劣化程度加剧，宏观性能指标呈现加速下降趋势。基于试验数据，建立了混凝土质量损失率、轴心抗压强度损失率和劈裂抗拉强度损失率的预测模型，并应用这些模型对硼酸腐蚀环境下混凝土结构的使用寿命进行了评估。研究成果可为核电厂混凝土结构的耐久性评估提供理论依据和技术参考。

关键词

混凝土 / 硼酸溶液 / 微观结构 / 宏观性能 / 退化

Abstract

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Introduction

During the operational lifespan of nuclear power plants, the accidental leakage of boric acid solutions is a potential event that can lead to the corrosion of concrete structures. This corrosive attack induces degradation in the macroscopic mechanical properties of concrete, posing a significant threat to the long-term structural integrity and operational safety of the facility. Consequently, a profound investigation into the mechanisms and patterns of this degradation is of paramount engineering importance for the accurate assessment of the long-term safety and service life of nuclear power plant structures. The general deterioration of concrete in aggressive environments is a well-studied field. The specific effect of boric acid as a prevalent chemical in nuclear power plant primary circuits on the microstructural and macro-mechanical performance evolution of concrete needs to be investigated. This work was to systematically investigate the degradation of concrete subjected to boric acid environments via integrating experimental tests with theoretical analysis. The primary objectives were to quantitatively characterize the deterioration of both microstructural and macro-mechanical properties in order to elucidate the influence and coupling effects of key factors (i.e., immersion time, boric acid concentration, temperature and water/binder ratio) and ultimately to develop predictive models for assessing the service life of concrete structures under the corrosive conditions.

Methods

A combined approach of experimental testing and theoretical analysis was employed to systematically investigate the degradation of concrete in boric acid environments. Concrete specimens with varying mix proportions, specifically different water/binder ratios, were prepared and exposed to boric acid solutions at different concentrations and temperatures, simulating a range of potential leakage scenarios. A comprehensive set of tests was conducted at regular intervals to monitor the evolution of concrete properties for an extended period (i.e., up to 360 d).

The experimental program included non-destructive and destructive tests to capture both microstructural changes and macro-mechanical degradation. Ultrasonic pulse velocity measurements were utilized as a non-destructive technique to probe the internal microstructural integrity and its evolution, providing an indicator of the extent of damage and micro-cracking induced by boric acid attack. Destructive tests were performed to quantify the mass loss, axial compressive strength loss, and splitting tensile strength loss. The mass loss rate was calculated to assess the leaching of cementitious components and overall material loss. The axial compressive strength loss rate and splitting tensile strength loss rate were determined to evaluate the degradation of key mechanical properties critical for structural load-bearing capacity.

Based on the extensive dataset obtained from these tests, a detailed quantitative analysis was performed. The effects of individual factors, immersion time, boric acid concentration, temperature, and water/binder ratio on the performance degradation indicators were analyzed. Furthermore, the interactions and coupling effects among boric acid concentration, temperature, and water/binder ratio were investigated. For the current volume of experimental data, a bilinear function approach was adopted for the preliminary analysis of these coupling effects. Finally, empirical prediction models for mass loss rate, axial compressive strength loss rate, and splitting tensile strength loss rate were proposed based on the experimental data, forming a basis for service life assessment.

Results and discussion

The experimental results reveal significant trends in concrete degradation under boric acid attack. The microstructural deterioration quantified through ultrasonic pulse velocity measurements shows consistent intensification with increasing boric acid concentration, temperature, and water/binder ratio. The relative ultrasonic pulse velocity is decreased by 15.49%-111.46% after 360 d, while the ultrasonic pulse velocity-time curve slope is reduced by 25.98%-134.37%, indicating an accelerated micro-damage. The factor interactions exhibit weak coupling characteristics. A distinctive two-phase behavior emerges across all the measured parameters. During initial immersion (i.e., 0-90 d), the negative values are obtained for mass loss rate and strength loss rates due to pore-filling effects of corrosion products and ongoing hydration. Beyond 90 d, all the parameters are positive and show monotonic increases, reflecting net material loss and structural deterioration. The degradation rates significantly amplify at higher boric acid concentrations, elevated temperatures, and increased water/binder ratios. Based on the comprehensive data, empirical predictive equations were proposed for mass loss and strength degradation, enabling quantitative service life assessment of concrete structures in nuclear power plants under a boric acid exposure.

Conclusions

The results revealed a clear two-phase degradation mechanism, driven by microstructural evolution. During the initial immersion period (i.e., 0-90 d), the formation of calcium metaborate crystals in the near-surface region that could not be fully corroded introduced a dominant filling effect. This led to a temporary increase in density and strength, manifested as negative mass and strength loss rates. Beyond 90 d, the development and progression of a fully corroded zone became a prevailing factor. This process could cause a sustained microstructural deterioration, which was effectively characterized by ultrasonic pulse velocity measurements. The deterioration intensified with increasing boric acid concentration, temperature, and water/binder ratio. Consequently, the mass loss and strength loss rates both became positive and exhibited a monotonic increasing trend. The empirical models were developed to predict the mass loss and strength loss, providing a reliable basis for assessing the structural performance and remaining a service life of concrete structures in nuclear power plants, thus offering valuable tools for durability and safety assessment.

Key words

concrete / boric acid solution / microstructure / macroscopic performance / degradation

引用本文

荣华, 耿岩, 陶钧, 周欣竹, 郑建军. 核电厂硼酸腐蚀混凝土微观结构和宏观性能的退化. 硅酸盐学报, 2026 , 54 (2) : 754 -767 . DOI: 10.14062/j.issn.0454-5648.20250550

Hua RONG, Yan GENG, Jun TAO, Xinzhu ZHOU, Jianjun ZHENG. Degradation of Microstructure and Macroscopic Performance of Boric Acid-Corroded Concrete in Nuclear Power Plants[J]. Journal of the Chinese Ceramic Society, 2026 , 54 (2) : 754 -767 . DOI: 10.14062/j.issn.0454-5648.20250550

基金

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优秀青年科学基金资助项目(52222808)
国家自然科学基金资助项目(52178255; 52278279)
北京市科技新星计划(20230484437)

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2026年第54卷第2期

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文章信息

doi: 10.14062/j.issn.0454-5648.20250550

接收时间：2025-07-14
首发时间：2026-10-27
出版时间：2026-02-20

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出版历史

收稿日期：2025-07-14
修回日期：2025-08-16

基金

优秀青年科学基金资助项目(52222808)

国家自然科学基金资助项目(52178255; 52278279)

北京市科技新星计划(20230484437)

作者信息

^1．中冶建筑研究总院有限公司，北京 100088

^2．中国核工业集团公司运维技术有限公司，杭州 311215

^3．浙江工业大学土木工程学院，杭州 310023

通讯作者:

耿岩（1988—），女，博士，高级工程师。

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https://castjournals.cast.org.cn/joweb/gsyxb/CN/10.14062/j.issn.0454-5648.20250550

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2种不同金属材料的力学参数

科 Family	属数 Number of genus	种数 Number of species	占总种数比例 Percentage of total species (%)	属 Genus	种数 Number of species	占总种数比例 Percentage of total species (%)
鹅膏菌科Amanitaceae	2	11	5.26	鹅膏菌属 Amanita	10	4.78
小菇科 Mycenaceae	2	12	5.74	丝盖伞属 Inocybe	5	2.39
多孔菌科 Polyporaceae	8	14	6.70	蜡蘑属 Laccaria	5	2.39
红菇科 Russulaceae	3	23	11.00	小皮伞属 Marasmius	6	2.87
				小菇属 Mycena	11	5.26
				光柄菇属 Pluteus	5	2.39
				红菇属 Russula	17	8.13
				栓菌属 Trametes	5	2.39

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