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Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel
Deng Ping1,2; Peng Qunjia1,3; Han En-Hou1; Ke Wei1; Sun Chen3; Xia Haihong3; Jiao Zhijie4
Corresponding AuthorPeng Qunjia(pengqunjia@yahoo.com)
2017-12-11
Source PublicationACTA METALLURGICA SINICA
ISSN0412-1961
Volume53Issue:12Pages:1588-1602
AbstractThe radiation-induced segregation (RIS) and microstructure evolution such as dislocation loops and cavities are major microstructural causes for the irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steel (SS) core components. While a couple of studies have been reported on the irradiation induced damage in nuclear grade (NG) austenitic SS, the evolution of dislocation loop density and size and its correlation with the mechanical properties have still remained incompletely understood. In addition, the correlation between the segregation at the grain boundary and that at the dislocation loop has received limited attentions. In particular, there is still a lack of a systematic study of the irradiation damage in domestically fabricated NG austenitic SS. In this work, the proton-irradiation induced microstructural damage in domestically fabricated 304NG SS was characterized, in an effort to correlate the RIS and the dislocation loop density and size with the irradiation dose, as well as the dislocation loop density and size with the radiation-induced hardening. The results revealed that the radiationinduced microstructure damage was mainly dislocation loops with a few micro-voids. The loop density was in the order of 10(22) m(-3) with an average size of <10 nm. The square root of the product of loop density and size (Nd)(0.5), scaled linearly with the square root of irradiation dose with a factor of 6.8x10(3) dpa(-0.5) . mm(-1). The loops were believed to be mainly responsible for the hardening in 304NG SS, which also scaled linearly with (Nd)(0.5) with a factor of 1.16x10(-2) HV0.025 . mm. A comparative analysis about the segregation at the grain boundary and at the dislocation loop was conducted. While the depletion of Cr and enrichment of Ni at the dislocation loop and grain boundary showed no difference, the enrichment of Si at the dislocation loop could be of about 6 times of that at the grain boundary. In addition, the loop density and loop size, as well as RIS and radiation-induced hardening were all increased by a higher dose and tended to saturate by a dose of 3.0 similar to 5.0 dpa.
Keywordnuclear grade stainless steel proton irradiation dislocation loop radiation-induced segregation radiation-induced hardening
Funding OrganizationInternational Science & Technology Cooperation Program of China ; National Natural Science Foundation of China
DOI10.11900/0412.1961.2017.00117
Indexed BySCI
Language英语
Funding ProjectInternational Science & Technology Cooperation Program of China[2014DFA50800] ; National Natural Science Foundation of China[51571204]
WOS Research AreaMetallurgy & Metallurgical Engineering
WOS SubjectMetallurgy & Metallurgical Engineering
WOS IDWOS:000416301600005
PublisherSCIENCE PRESS
Citation statistics
Cited Times:5[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/125522
Collection中国科学院金属研究所
Corresponding AuthorPeng Qunjia
Affiliation1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China
2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Liaoning, Peoples R China
3.State Power Investment Corp, Res Inst, Beijing 102209, Peoples R China
4.Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
Recommended Citation
GB/T 7714
Deng Ping,Peng Qunjia,Han En-Hou,et al. Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel[J]. ACTA METALLURGICA SINICA,2017,53(12):1588-1602.
APA Deng Ping.,Peng Qunjia.,Han En-Hou.,Ke Wei.,Sun Chen.,...&Jiao Zhijie.(2017).Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel.ACTA METALLURGICA SINICA,53(12),1588-1602.
MLA Deng Ping,et al."Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel".ACTA METALLURGICA SINICA 53.12(2017):1588-1602.
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