Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service
In this paper, the performance degradation behavior of fuel cladding material 20Cr25NiNb for the British Advanced Gas Reactor (AGR) is reviewed in detail, which is a strong guideline for the material selection of supercritical carbon dioxide cooled reactors. The degradation behavior during in-core s...
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| Format: | Article |
| Language: | English |
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Frontiers Media S.A.
2022-11-01
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| Series: | Frontiers in Materials |
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| Online Access: | https://www.frontiersin.org/articles/10.3389/fmats.2022.1058045/full |
| _version_ | 1828093009065934848 |
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| author | Ming Shu Ming Shu Yongduo Sun Qin Zhou Jun Xiao Zhaodandan Ma Xiao Liu |
| author_facet | Ming Shu Ming Shu Yongduo Sun Qin Zhou Jun Xiao Zhaodandan Ma Xiao Liu |
| author_sort | Ming Shu |
| collection | DOAJ |
| description | In this paper, the performance degradation behavior of fuel cladding material 20Cr25NiNb for the British Advanced Gas Reactor (AGR) is reviewed in detail, which is a strong guideline for the material selection of supercritical carbon dioxide cooled reactors. The degradation behavior during in-core service mainly includes high-temperature creep, thermal aging and mechanical property degradation caused by neutron irradiation (fission gas products, helium embrittlement and irradiation sensitization) and CO2 (oxidation and carburizing). Long-term service in AGR leads to coarsening of the second phase and precipitation of harmful phases such as σ, leading to performance degradation of the cladding. A point that should require special attention is that intergranular stress corrosion cracking (IGSCC) and intergranular attack (IGA) problems occur during wet storage of spent fuel. |
| first_indexed | 2024-04-11T06:38:09Z |
| format | Article |
| id | doaj.art-7b812819bcbb4067844242c5f142a074 |
| institution | Directory Open Access Journal |
| issn | 2296-8016 |
| language | English |
| last_indexed | 2024-04-11T06:38:09Z |
| publishDate | 2022-11-01 |
| publisher | Frontiers Media S.A. |
| record_format | Article |
| series | Frontiers in Materials |
| spelling | doaj.art-7b812819bcbb4067844242c5f142a0742022-12-22T04:39:37ZengFrontiers Media S.A.Frontiers in Materials2296-80162022-11-01910.3389/fmats.2022.10580451058045Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during serviceMing Shu0Ming Shu1Yongduo Sun2Qin Zhou3Jun Xiao4Zhaodandan Ma5Xiao Liu6Nuclear Power Institute of China (NPIC), Chengdu, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, ChinaNuclear Power Institute of China (NPIC), Chengdu, ChinaInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, ChinaNuclear Power Institute of China (NPIC), Chengdu, ChinaNuclear Power Institute of China (NPIC), Chengdu, ChinaNuclear Power Institute of China (NPIC), Chengdu, ChinaIn this paper, the performance degradation behavior of fuel cladding material 20Cr25NiNb for the British Advanced Gas Reactor (AGR) is reviewed in detail, which is a strong guideline for the material selection of supercritical carbon dioxide cooled reactors. The degradation behavior during in-core service mainly includes high-temperature creep, thermal aging and mechanical property degradation caused by neutron irradiation (fission gas products, helium embrittlement and irradiation sensitization) and CO2 (oxidation and carburizing). Long-term service in AGR leads to coarsening of the second phase and precipitation of harmful phases such as σ, leading to performance degradation of the cladding. A point that should require special attention is that intergranular stress corrosion cracking (IGSCC) and intergranular attack (IGA) problems occur during wet storage of spent fuel.https://www.frontiersin.org/articles/10.3389/fmats.2022.1058045/full20Cr25NiNbAGRcladdingaustenitic heat resistant steelperformance degradationirradiation |
| spellingShingle | Ming Shu Ming Shu Yongduo Sun Qin Zhou Jun Xiao Zhaodandan Ma Xiao Liu Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service Frontiers in Materials 20Cr25NiNb AGR cladding austenitic heat resistant steel performance degradation irradiation |
| title | Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service |
| title_full | Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service |
| title_fullStr | Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service |
| title_full_unstemmed | Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service |
| title_short | Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service |
| title_sort | overview on performance degradation behavior of 20cr25ninb steel for gas cooled reactor cladding during service |
| topic | 20Cr25NiNb AGR cladding austenitic heat resistant steel performance degradation irradiation |
| url | https://www.frontiersin.org/articles/10.3389/fmats.2022.1058045/full |
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