Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment
This study systematically investigated the incipient corrosion behavior of Fe-13Cr-4.5Al (wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months under simulated PWR conditions (18.6 MPa and 360 °C) in an autoclave system. The corrosion induced two types of structure of...
| Main Authors: | , , , , , , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2023-06-01
|
| Series: | Materials & Design |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S0264127523003635 |
| _version_ | 1797807267482959872 |
|---|---|
| author | Zheng Qu Chuiyi Meng Juncheng Huang Yuchang Mei Yinmeng Zhang Jiaojiao Ma Wenguan Liu Hui Wang Xiujie He |
| author_facet | Zheng Qu Chuiyi Meng Juncheng Huang Yuchang Mei Yinmeng Zhang Jiaojiao Ma Wenguan Liu Hui Wang Xiujie He |
| author_sort | Zheng Qu |
| collection | DOAJ |
| description | This study systematically investigated the incipient corrosion behavior of Fe-13Cr-4.5Al (wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months under simulated PWR conditions (18.6 MPa and 360 °C) in an autoclave system. The corrosion induced two types of structure of oxide scale. FeCrAl alloys corroded for 3 months exhibited a duplex structure containing outer oxide particles and an inner Cr-rich spinel. During the corrosion test lasting 3–4 months, a triplex structure containing outer oxide particles, an inner compact Cr-rich spinel layer, and a porous spinel layer was observed. Moreover, Cr enriched at the periphery of outer oxides, indicating the formation of FeCr2O4 spinel oxide. |
| first_indexed | 2024-03-13T06:20:01Z |
| format | Article |
| id | doaj.art-bc6d8559d9af4392b8e0ae47e7165853 |
| institution | Directory Open Access Journal |
| issn | 0264-1275 |
| language | English |
| last_indexed | 2024-03-13T06:20:01Z |
| publishDate | 2023-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Materials & Design |
| spelling | doaj.art-bc6d8559d9af4392b8e0ae47e71658532023-06-10T04:26:55ZengElsevierMaterials & Design0264-12752023-06-01230111948Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environmentZheng Qu0Chuiyi Meng1Juncheng Huang2Yuchang Mei3Yinmeng Zhang4Jiaojiao Ma5Wenguan Liu6Hui Wang7Xiujie He8Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaSino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, ChinaScience and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610041, Sichuan, China; Interdisciplinary Materials Research Center, Institute for Advanced Study, Chengdu University, Chengdu 610106, Sichuan, China; Corresponding authors at: Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610041, Sichuan, China (H. Wang); Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, China (X. He).Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, China; Corresponding authors at: Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610041, Sichuan, China (H. Wang); Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, Guangdong, China (X. He).This study systematically investigated the incipient corrosion behavior of Fe-13Cr-4.5Al (wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months under simulated PWR conditions (18.6 MPa and 360 °C) in an autoclave system. The corrosion induced two types of structure of oxide scale. FeCrAl alloys corroded for 3 months exhibited a duplex structure containing outer oxide particles and an inner Cr-rich spinel. During the corrosion test lasting 3–4 months, a triplex structure containing outer oxide particles, an inner compact Cr-rich spinel layer, and a porous spinel layer was observed. Moreover, Cr enriched at the periphery of outer oxides, indicating the formation of FeCr2O4 spinel oxide.http://www.sciencedirect.com/science/article/pii/S0264127523003635FeCrAl alloyAccident-tolerant fuelCorrosionSimulated PWR environment |
| spellingShingle | Zheng Qu Chuiyi Meng Juncheng Huang Yuchang Mei Yinmeng Zhang Jiaojiao Ma Wenguan Liu Hui Wang Xiujie He Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment Materials & Design FeCrAl alloy Accident-tolerant fuel Corrosion Simulated PWR environment |
| title | Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment |
| title_full | Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment |
| title_fullStr | Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment |
| title_full_unstemmed | Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment |
| title_short | Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment |
| title_sort | mechanistic study of incipient corrosion for nuclear grade lean cr fecral alloys in a simulated pwr environment |
| topic | FeCrAl alloy Accident-tolerant fuel Corrosion Simulated PWR environment |
| url | http://www.sciencedirect.com/science/article/pii/S0264127523003635 |
| work_keys_str_mv | AT zhengqu mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT chuiyimeng mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT junchenghuang mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT yuchangmei mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT yinmengzhang mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT jiaojiaoma mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT wenguanliu mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT huiwang mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment AT xiujiehe mechanisticstudyofincipientcorrosionfornucleargradeleancrfecralalloysinasimulatedpwrenvironment |