超临界水冷堆候选包壳材料研究进展与思考

张乐福; 黄涛; 苏豪展; 高阳; 郭相龙; 沈朝; 陈凯

doi:10.13832/j.jnpe.2025.01.0183

超临界水冷堆候选包壳材料研究进展与思考

doi: 10.13832/j.jnpe.2025.01.0183

张乐福^1,,
黄涛¹,
苏豪展²,
高阳³,
郭相龙¹,
沈朝⁴,
陈凯¹

1.
上海交通大学核科学与工程学院，上海，200240
2.
中国原子能科学研究院，北京，102413
3.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213
4.
上海交通大学材料科学与工程学院，上海，200240

基金项目: 国家重点研发计划（2018YFE0116200）

详细信息

作者简介:
张乐福（1967—），男，研究员，现主要从事反应堆材料与水化学方面的研究，E-mail: lfzhang@sjtu.edu.cn

中图分类号: TL334
计量
- 文章访问数: 17
- HTML全文浏览量: 7
- PDF下载量: 1
- 被引次数: 0
出版历程
- 收稿日期: 2024-04-16
- 修回日期: 2024-12-11
- 刊出日期: 2025-02-15

Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors

1.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
China Institute of Atomic Energy, Beijing, 102413, China
3.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
4.
School of Material Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China

摘要

摘要: 超临界水冷堆（SCWR）具有热效率高、结构简单等技术优势，是第四代核能系统国际论坛推荐的6个堆型之一。本文首先回顾了SCWR的包壳设计要求和主要性能挑战，然后对经过较多测试的商用候选包壳材料的均匀腐蚀、应力腐蚀及辐照性能进行了回顾。铁素体/马氏体（F/M）钢、奥氏体不锈钢及镍基合金均存在某方面的性能不足。最后，介绍了近年来新兴的SCWR候选包壳材料，包括新型含铝奥氏体不锈钢、氧化物弥散强化钢、梯度材料及其他组织改进技术的研究进展。
- 超临界水冷堆 /
- 燃料包壳材料 /
- 均匀腐蚀 /
- 应力腐蚀开裂
Abstract: The Supercritical Water-cooled Reactor (SCWR) is one of the six reactor types recommended by the Generation IV International Forum (GIF) due to its high thermal efficiency and simple structural design. This paper provides an overview of the design requirements and key performance challenges for SCWR cladding material, including the general corrosion, stress corrosion and irradiation properties of commercial candidate cladding materials that have been tested a lot. Ferrite/Martensite (F/M) steel, austenitic stainless steel and nickel-based alloy all have some performance deficiencies. Finally, the recent research progress of novel SCWR candidate cladding materials is reviewed, including alumina-forming austenitic (AFA) steels, oxide dispersion strengthened (ODS) steels, functionally gradient materials and microstructure improvement techniques.
- Supercritical Water-cooled Reactor /
- Fuel cladding material /
- General corrosion /
- Stress corrosion crack

HTML全文

图 1 商用候选包壳材料腐蚀增重^[17-19]

DO—溶解氧

Figure 1. Corrosion Weight Gain of Commercial Candidate Cladding Materials^[17-19]

下载: 全尺寸图片幻灯片

图 2 商用候选包壳材料的典型腐蚀截面形貌

BC—背散射电子成像

Figure 2. Typical Corrosion Cross-section Morphology of Commercial Candidate Cladding Materials

下载: 全尺寸图片幻灯片

图 3 氩气与SCW环境的CGR^[30-31]

K—应力强度因子

Figure 3. Comparison of Crack Growth Rates in Pure Argon and SCW Environment^[30-31]

下载: 全尺寸图片幻灯片

图 4 镍基合金与奥氏体不锈钢CGR与温度的关系^[32]

Q—激活能

Figure 4. Relationship between CGR and Temperature of Nickel-based Alloys and Austenitic Stainless Steels^[32]

下载: 全尺寸图片幻灯片

图 5 温度、合金类别、辐照剂量与SCC的关系^[36]

dpa—原子平均离位

Figure 5. Relationship between Temperature, Alloy Composition, Radiation Dose and SCC^[36]

下载: 全尺寸图片幻灯片

图 6 Al质量百分数与AFAs耐腐蚀性能的关系^[49]

Δw—腐蚀增重；t—时间

Figure 6. Relationship between Al Content and Corrosion Resistance of AFAs^[49]

下载: 全尺寸图片幻灯片

图 7 ODS钢耐腐蚀性能与Cr质量百分数的关系^[19]

Figure 7. Relationship between Cr Content and Corrosion Resistance of ODS steel^[19]

下载: 全尺寸图片幻灯片

图 8 表面粗加工提高奥氏体不锈钢800H耐腐蚀性能^[23]

Figure 8. Effect of Surface State on Corrosion Performance of Austenitic Stainless Steel 800H^[23]

下载: 全尺寸图片幻灯片

图 9 表面梯度处理工艺平衡包壳材料的综合性能

Figure 9. Surface Gradient Treatment to Balance Comprehensive Performance of Candidate Cladding Materials

下载: 全尺寸图片幻灯片

表 1 SCWR商用候选包壳材料及其性能比较^[8]

Table 1. Comparison of SCWR Commercial Candidate Cladding Materials and Their Properties^[8]

合金类型	代表材料	高温力学性能	耐高温腐蚀性能	耐高温蠕变性能	抗辐照/中子性能
F/M钢（BCC相）	T91、P92、P122、HT9、NF616	优秀	较差	一般	优秀
奥氏体不锈钢（FCC相）	310S、800H、HR3C、304、316L	优秀	一般	较差	一般
镍基合金（FCC相）	690、625、PE16、 C276、X750	优秀	优秀	一般	较差

下载: 导出CSV

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