兰州大学机构库
Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients
Huang, Zi-Nan1; Li, Yun-Xiang1; Li, Song1; Xi, Bin1; Zhang, You-Peng1; Meng, Lu1; Wanga, Di-Si1; Liu, Bo1; Gu, Long1,2,3; Peng, Tian-Ji1,3; Zhang, Lu1,3; Jiang, Wei1,3; Wallenius, Janne4
2023-12-15
Online publication date2023-08
Source PublicationANNALS OF NUCLEAR ENERGY   Impact Factor & Quartile
ISSN0306-4549 ; 1873-2100
Volume194
page numbers8
AbstractThe China Initiative Accelerator Driven System (CiADS) was proposed by China Academy of Science since 2015. The subcritical reactor in CiADS is a liquid Lead Bismuth Eutectic (LBE) cooled fast reactor. When the reactor core is in operation, the LBE coolant will directly contact and corrode the inner surface of reactor vessel. Due to the high temperature, the corrosion will be more severe. If the stress on the reactor vessel exceeds the limit, the plastic deformation will occur, leading to the generation and expansion of defects and cracks, and the safety of the reactor will be affected. Therefore, evaluating the stress field of the reactor vessel under different operating conditions is a very important research project. In this paper, the finite element analysis software ADINA was applied to analyze the reactor vessel in CiADS, and the ASME Code was used as stress assessment standards. We can preliminarily prove that the stress assessments of the vessel during the postulated Unprotected Loss of Flow (ULOF) accidents satisfy the requirements of ASME Code. The limit reactivity insertion to protect the vessel from plastic deformation is 0.58$ in the postulated Unprotected Transient over Power (UTOP) accidents based on our current results. Therefore, we can preliminarily conclude that the current material selection and structural design of the reactor vessel in CiADS could survive most of the postulated transient accidents considering the stress effect.
KeywordFinite element analysis CiADS Reactor vessel ADINA Stress
PublisherPERGAMON-ELSEVIER SCIENCE LTD
DOI10.1016/j.anucene.2023.110067
Indexed BySCIE
Language英语
WOS Research AreaNuclear Science & Technology
WOS SubjectNuclear Science & Technology
WOS IDWOS:001054960900001
Original Document TypeArticle
Citation statistics
Document Type期刊论文
Identifierhttps://ir.lzu.edu.cn/handle/262010/568714
Collection兰州大学
Corresponding AuthorZhang, You-Peng
Affiliation
1.Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China;
2.Lanzhou Univ, Inst Nucl Sci & Technol, Lanzhou 730000, Peoples R China;
3.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China;
4.KTH Royal Inst Technol, Div Nucl Engn, S-10691 Stockholm, Sweden
Recommended Citation
GB/T 7714
Huang, Zi-Nan,Li, Yun-Xiang,Li, Song,et al. Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients[J]. ANNALS OF NUCLEAR ENERGY,2023,194.
APA Huang, Zi-Nan.,Li, Yun-Xiang.,Li, Song.,Xi, Bin.,Zhang, You-Peng.,...&Wallenius, Janne.(2023).Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients.ANNALS OF NUCLEAR ENERGY,194.
MLA Huang, Zi-Nan,et al."Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients".ANNALS OF NUCLEAR ENERGY 194(2023).
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